List of archived documents and reports from the
NEA Committee on Reactor Physics (1973-1993) 
NEACRP-A Series

In order to find out whether you have access to any of these documents please submit an enquiry to the NEA Secretariat.


NEACRP-A- 217
   Check List of Working Rules of the Nuclear Energy Agency Committee on Reactor Physics
   April 1974

NEACRP-A- 218
   Report on the Activities of the NEA Neutron Data Compilation Centre of Interest to NEACRP
   March 1973 - March 1974

NEACRP-A- 219
   Report on the Activity of the NEA Computer Program Library of Interest to NEACRP
   May 1973 - May 1974

NEACRP-A- 220
   The Physics of CANDU On-Power Fuelling: from Design Objective to Pickering Demonstration
   Pasanen, A.A.

NEACRP-A- 221
   Report on the IAEA Workshop on 'Fusion Reactor Design Problems' held in
   Culham (UK) on 29th Jan. - 15th Feb. 1974
   Spano, A.H.
   30th May 1974

NEACRP-A- 222
   On the Validity of Adjusted Cross Sections
   Kuroi, H. and Hirota, J.
   May 1974

NEACRP-A- 223
   Comments on Sodium Void Effect
   Shirakata, K., Kuroi, H. and Hirota, J.
   May 1974

NEACRP-A- 224
   Some Recent Results of Sodium Void Analysis and Related Problems
   (PNC CN 241 74-2)
   Zukeran, A., Iijima, S., Yamamoto, M. and Kobayashi, T.
   May 1974

NEACRP-A- 225
   Review of Fast Reactor Physics Activities Relevant to LMFBR Programme in PNC (Japan)
   (PNC SN 241 74-05)
   Kobayashi, S.
   June 1974

NEACRP-A- 226
   International Symposium on Physics of Fast Reactors (Report), held in Tokyo
   16th - 19th October 973

NEACRP-A- 227
   Report on the 17th EANDC Meeting, held in Tokyo
   Hirota, J.
   25th - 29th March 1974

NEACRP-A- 228
   Discussion of Target Accuracies of Core Power Distributions in Light Water Reactors
   Norinder, O.
   May 1974

NEACRP-A- 229
   A Review of the Sodium Void Coefficient and Ways of Reducing it to Produce Safer Fast Reactors
   Smith, M.F.
   April 1974

NEACRP-A- 230
   The Analysis of One-Dimensional Reactor Kinetic Benchmark Computations
   Sidell, J.

NEACRP-A- 231
   CSEWG Benchmark Specifications
   1974

NEACRP-A- 232
   Target Accuracies for Commercial-Sized Reactors
   Lewellen, J.W.
   1974

NEACRP-A- 233
   The Accuracy in the Prediction of Physics Parameters of Fast Breeder Reactor
  (PNC SN 241 74-04)
   Kobayashi, A. and Kinjo, K.
   June 1974

NEACRP-A- 234
   Summary Record of the Seventeenth Meeting of the NEACRP, held at Cadarache,  (France)
   E. Hellstrand
   4th-7th June 1974

NEACRP-A- 235
   CCDN: Past, Present, Future
   June 1974

NEACRP-A- 236
   Adjustments of Neutron Data from ENDF/B-III by Using Integral Data in a Least-Squares Fit
   Haeggblom, H.
   June 1974

NEACRP-A- 237
   Reactor Physics Aspects of the Oklo Phenomenon
   Naudet R.

NEACRP-A- 238
   Comparison of the Cross-Section Sensitivity of the Tritium Breeding Ratio in Various Fusion-Reactor Blankets (ORNL-TM-4696)
   Alsmiller, Jr., R.G., Santoro, R.T., Barish, J. and Gabriel, T.A.
   October 1974

NEACRP-A- 239
   Progress Report on the Activities of the NEA Committee on the Safety of Nuclear Installations,
   note prepared by the CSNI Secretariat for the 18th meeting of the NEA-CRP

NEACRP-A- 240
   Fission Product Afterheat at Short Times (10 - 104 sec) after Shutdown
   James, M.F.
   June 1975

NEACRP-A- 241
   Estimation of Decay Data for Short-Lived Fission Products, Decay Heat Nuclear Data Working Group of the Japanese Nuclear Data Committee
   June 1975

NEACRP-A- 242
   Reactor Physics Aspects of Gas-Cooled Fast Reactors (in German) , except from KFK 2375/EUR 4575 (1973)

NEACRP-A- 243
   Design and Safety Considerations for 1000 MWe Gas-Cooled Fast Reactor
   Dalle Donne, M. and Goetzmann, C.A.

NEACRP-A- 244
   Preliminary Results of Integral Experiment on Fusion-Fission Hybrid Blanket Assemblies
   Maekawa, H. and Seki, Y.
   May 1975

NEACRP-A- 245
   Experiments on Neutron Streaming along Void Channels
   Kaneko, Y. and Tsuchihashi, K.

NEACRP-A- 246
   Outline of Model and Calculations for Proposed Internal Collaboration Exercise to Discover the Dependence of Reactor Performance Properties on the Choice of Nuclear Data

NEACRP-A- 247
   Proposed Standard Group Structure for Nuclear Data for Reactors
   Askew, J.R., Butler, J., Campbell, C.G. and Rowlands, J.L.
   June 1975

NEACRP-A- 249
   Summary Record of the Decisions and Conclusions Reached by the NEA-CRP
   at its Eighteenth Meeting, held at C.D.C. Bologna (Italy)
   Royen, J.
   9th - 13th June 1975

NEACRP-A- 250
   Fission Product Data for Nuclear Technology Applications
   Hemming, P.

NEACRP-A- 251
   Transformation of Actinides and Fission Products by Neutron Irradiation
   Hemming, P.

NEACRP-A- 252
   U.S. Results for the IAEA Three-Dimensional Neutron Diffusion Problem

NEACRP-A- 253
   The transmutation of Radioactive Reactor Waste (Australian Atomic Energy Commission)
   J.R. Harries

NEACRP-A- 254
   Concepts for the Nuclear Transmutation of Radioactive Waste from Fission Reactors at present under discussion
   Hage, W., Schmidt, E.

NEACRP-A- 255
   Summary Record of the 18th Meeting of the NEACRP Committee, Bologna (Italy)
   9-13 June 1975

NEACRP-A- 256
   NEACRP Benchmark BWR Lattice Cell Problems (UK) (2 parts)
   J.R. Askew (part 1), M.J. Halsall (part 2), 1976
  
NEACRP-A- 258
   Review of Fast Reactor Physics Activities relevant to LMFBR Programme in PNC, (Japan)
   T. Inoue

NEACRP-A- 259
   Some Reactor Physics Problems related to LMFBR Safety (Japan)
   K. Aizawa, T. Inoue

NEACRP-A- 260
   A Study of Anisotropic Diffusion Effect in Plate Lattice Assembly (Japan)
   K. Shirakata, T. Iijima, K. Yamagishi

NEACRP-A- 261
   Treatment of Cruciform Control Rods in CASMO (Sweden)
   Malte Edenius

NEACRP-A- 262
   Intercomparison of Fission Chamber Standard (UK)
   J.E. Sanders

NEACRP-A- 263
   Summary of Current NEACRP Views on Fast Reactor Breeding Assessment  (France)
   J.Y. Barre

NEACRP-A- 264
   Brief Review of Fusion-Reactor Neutronics in the US
   F.C. Maienschein

NEACRP-A- 265
   Benchmark Calculation of DT Fusion Machine (Italy)

NEACRP-A- 266
   Bidimensional Calculation of Neutron Flux for JET Outline (Italy)
   Edmondo Pedretti & Luciano Tondinelli

NEACRP-A- 267
   Neutronic and Photonic Studies on Fusion Reactor Blankets with Low Lithium and Tritium Inventories (Netherlands)
   K.A. Vorschuur, H. Brockmann

NEACRP-A- 268
   On the Possibility of using a Plasma Focus Machine as Neutron Source for Cross-Section Measurements by the Activation Method (Italy)
   R. Abbondanza, E. Pedretti

NEACRP-A- 269
   On the Prospects of Mixed Fusion-Fusion Energy Systems (Italy)
   Ugo Farinelli

NEACRP-A- 270
   Radioactivity and Afterheat of FINTOR and Related Problems of Maintenance and Waste Disposal (EURATOM)

NEACRP-A- 271
   Sensitivity Analysis of Cross-Section Uncertainties related to the JET Machine (Italy)

NEACRP-A- 272
   Specifications for an Internal Comparison Calculation of a large Sodium-cooled Fast Breeder Reactor (US)

NEACRP-A- 273
   Some Comments on the Impact of Thermal Near Breeders on Uranium Utilization  (US)
   C.E. Till, Y.I. Chang

NEACRP-A- 274
   Simulation of an HCDA Sequence on the ZPPR Critical Facility (US)
   R.E. Kaiser, C.L. Beck

NEACRP-A- 275
   On the Extrapolation of ZPR Sodium Void Measurements to the Power Reactor  (US)
   C.L. Beck, P.J. Collins, M.J. Lineberry, G.L. Grasseschi

NEACRP-A- 276
   Validation results for the DSX Cell Homogenization CODE (US)
   D.C. Wade

NEACRP-A- 277
   Model Problems to validate the MC2-II/DSX/Benoist Procedures for generating Cell-Average Broad Group Cross Sections and Anisotropic Diffusion Coefficients in ZPR Plate Cells (US)

NEACRP-A- 278
   Belgium Plutonium Recycle Program (Belgium)
   H. Bairiot, J. Debrue

NEACRP-A- 279
   New Developments in Generalized Perturbation Methods in the Nuclide Field (Italy)
   A.Gandini, M. Salvatores, L. Tondinelli

NEACRP-A- 280
   Overview of US Activities in Noise Analysis for Nuclear Power Reactors (US)
   R.C. Kryter

NEACRP-A- 281
   The Reactor Physics Problems of LMFBR Safety (UK)
   A.R. Baker

NEACRP-A- 282
   Some suggestions relating to Safety Oriented Work for NEACRP (UK)
   F.J. Fayers

NEACRP-A- 283
   Effects of Fast Breeder Characteristics on Consumption and Expenditures related to Electric Power Generation. An Assessment for the European Community (EURATOM)
   G. Graziani, C. Zanantoni

NEACRP-A- 284
   Neutron-Induced Activation in JET (Chapter V from document EUR-JET-R5)

NEACRP-A- 286
   Preliminary announcement of specialist meeting on cross-sections in structural materials.

NEACRP-A- 287
   NEACRP member's reports on national activities on fission product decay data

NEACRP-A- 288
   Summary Record of the 19th Meeting of the Committee
   1976
  
NEACRP-A- 289
   Full Minutes of the 19th Meeting of the Committee

NEACRP-A- 291
   Consideration of UK., German and French Category I requests for Nuclear Data
   C.G. Campbell, 1977

NEACRP-A- 292
   Review of fast reactor physics activities relevant to the LMFBR programme in PNC (Japan)
   T. Inoue

NEACRP-A- 293
   Modified diffusion theory analysis of simulated meltdown experiments (Japan)
   Yuji Seki and Makoto Sasaki

NEACRP-A- 294
   Test of FP data in JENDC-I by using the integral data (Japan)
   Y. Kikuchi and A. Hasegawa

NEACRP-A- 295
   On the physics of LWR-FUGEN (Japan)
   T. Haga, M. Matsumoto, H. Kato, and S. Hattori

NEACRP-A- 296
   A study on fission rate and gamma-ray heat generation in a fast reactor  (Japan)
   K. Koyama, N. Sasamoto, M. Obu, S. Tanaka, Y. Furuta, H. Kuroi, and  J. Hirota

NEACRP-A- 297
   Study on sodium void reactivity worth predictional method (Japan)
   T. Kamei, T. Yoshida, K. Murakami, S. Iijima

NEACRP-A- 298
   The application of sensitivity analysis to the identification of data  requirements for shielding (UK)
   A.K. McCraken

NEACRP-A- 299
   The measurement of gamma-ray energy deposition in the zero-power fast reactor ZEBRA with Li7F thermoluminescent dosimeters (UK)
   A.D. Knipe

NEACRP-A- 300
   The sodium void effect: The influence of heterogeneity (UK)
   M.J. Grimstone and A.T.D. Butland

NEACRP-A- 301
   The sodium void effect: A review of calculational methods and experiments.  (UK)
   A.T.D. Butland and M.J. Grimstone

NEACRP-A- 302
   Studies of low sodium void reactivity cores (UK)
   C.G. Campbell

NEACRP-A- 303
   The determination of peak pellet rating (UK)
   J.R. Askew

NEACRP-A- 304
   The thermoluminescent dosimeter measurement of gamma-ray energy deposition distributions in reactor shields (USA)
   P.N. Stevens, C.E. Clifford, F.J. Muckenthaler, and W. Yoon

NEACRP-A- 305
   Recent developments in sensitivity analysis in the US (USA)
   E.M. Oblow

NEACRP-A- 306
   Fission-product energy release for times following thermal-neutron fission of 235U between 2 and 14,000 s (USA)
   J.K. Dickens, J.F. Emery, T.A. Love, J.W. McConnell, K.J. Northeutt, R.W. Peelle, and H. Waever

NEACRP-A- 307
   Fichier de donnees produits de fission (France)

NEACRP-A- 308
   Proposal for GCFR-steam entry benchmarks (Germany)
   E.Kiefhaber

NEACRP-A- 309
   First comparison of some results obtained at Karlsruhe and Wuerenlingen for GCFR-steam entry benchmarks (Germany)
   E. Kiefhaber

NEACRP-A- 310
   Influence of various nuclear data sets on the prediction of actinides in fast reactor fuel after discharge (Germany)
   H. Kuesters and M. Lalovic

NEACRP-A- 311
   Announcement of ANL Benchmark Meeting

NEACRP-A- 312
   Summary Record of 20th Meeting (Petten)
   June 1977

NEACRP-A- 313
   Full Minutes of the 20th Meeting of the Committee

NEACRP-A- 314
   (Revised) List of NEACRP Category 1 requests

NEACRP-A- 315
   Report on GEEL Meeting on Cross Sections for Structural Materials.  Recommendations and conclusions from the NEANDC/NEACRP Specialist Meeting on the neutron data of structural materials for fast reactors
   DEC. 1977

NEACRP-A- 316
   Shielding problems in fast reactors. NEACRP review on status of fast reactor physics
   U. Farinelli, R. Nicks,  1978
  
NEACRP-A- 318
   Sensitivity Analysis of Build-up and Decay of Actinides in Fast Reactors (Japan)
   H. Mitani

NEACRP-A- 319
   Atomistic Simulation of Radiation Defects in Various Crystal Structures (Japan)
   Y. Taji

NEACRP-A- 320
   A Study of the Heterogeneous Core Characteristics (Japan)
   K. Tsutsumi

NEACRP-A- 321
   NEA Data Bank Report (Secretariat)

NEACRP-A- 322
   Comparison of Neutron Diffusion Theory Codes in Two and Three Space Dimensions using a Sodium Cooled Fast Reactor Benchmark (UK)
   A.T.D. Butland

NEACRP-A- 323
   The Spatial Averaging of Cross Sections for use in Transport Theory Reactor Calculations, with an Application to Control Rod Fine Structure Homogenisation (UK)
   J.L. Rowlands et Al.

NEACRP-A- 324
   The Effects of Subassembly Heterogeneity and Material Boundaries on the Sodium Voiding and Doppler Effects in a Sodium Cooled Fast Reactors (UK)
   A.T.D. Butland

NEACRP-A- 325
   The Calculation of Streaming Corrected Diffusion Coefficients for Fast Reactors (UK)
   M.H. Grimstone

NEACRP-A- 326
   The IAEA Activities in Reactor Physics (IAEA)
   E.A. Khodarev

NEACRP-A- 327
   Experimentelle un Theoretische Untersuchungen zur Reaktivitaetsbindung von Absorberelementen in HTR-systemen (Germany)
   V. Drueke et Al.

NEACRP-A- 328
   Nodal and Coarse Mesh Codes (Germany)
   S. Langenbuch

NEACRP-A- 329
   Constants System OSCAR-76 (USSR)
   Ju. G. Bobkov

NEACRP-A- 330
   The Denatured Uranium-Thorium Fuel Cycle (Canada)
   D. Hamel

NEACRP-A- 331
   Benchmark Experiments Related to Actinide Production in Thermal Reactors
   (Belgium)

NEACRP-A- 332
   Fission-Product Nuclear Data Project Progress Report (Netherlands)
   H. Gruppelaar

NEACRP-A- 333
   Information note on dpa calculations (Belgium)

NEACRP-A- 334
   Adjustment of evaluated microscopic data on the basis of evaluated integral experiments (USSR)
   L.N. Usachev et Al.

NEACRP-A- 335
   Determination of transactinide nuclear data required accuracy for burn-up  calculation in fast reactors (USSR)
   L.N. Usachev et Al.

NEACRP-A- 336
   A global approach to fuel cycles? (Italy)
   U. Farinelli

NEACRP-A- 337
   A Preliminary Evaluation of the Technical Aspects of I.N.F.C.E. (Italy)
   U. Farinelli

NEACRP-A- 338
   Benchmark Experiments with Thorium in Fast Reactor Lattices (Switzerland)
   U. Schmocker et Al.

NEACRP-A- 339
   A U-Pu-Np Cycle in the GCFR (Switzerland)
   P. Wydler et Al.

NEACRP-A- 340
   Application of Heterogeneous Theory to PWR Studies (UK)
   J.R. Askew et Al.

NEACRP-A- 341
   Actinide Depletion Studies (USA)
   J.W. Lewellen

NEACRP-A- 342
   Actinide Monitoring Status Report (Belgium)
   G. Birkhoff

NEACRP-A- 343
   Neutronics in the Toroidal Belt-Geometry of a Screw Pinch Reactor (Netherlands)
   K.A. Verschuur

NEACRP-A- 344
   A Sensitivity Study for Two-Zone Conventional LMFBR Cores (USA)
   P.J. Collins

NEACRP-A- 345
   Fuel Handling, Reprocessing and Waste and Related Nuclear Data Aspects (Germany)
   H. Kuesters

NEACRP-A- 346
   NEANDC Monographs - Draft Reply (UK)
   J.R. Askew

NEACRP-A- 347
   NEACRP Documentation Distribution (Secretariat)

NEACRP-A- 348
   Summary Record of 21st Meeting (produced in Paris)

NEACRP-A- 349
   Specialists Meeting on Calculation of 3-D rating distributions in operating  reactors (Paris)
   26th - 28th November 1979

NEACRP-A- 350
   Summary Report of discussions at NEA Data Bank
   19th January 1979

NEACRP-A- 351
   Note from J.J. Schmidt (IAEA). Action 9 of 21st Committee Meeting - Succession of Transactinide Nuclear Data Meetings (covering memorandum  from J. Rosen)

NEACRP-A- 352
   Distribution list for NEACRP Documents (Categories 'A' and 'L' only) -  replacing document NEACRP-U-45

NEACRP-A- 353
   Summary Record of 21st Meeting (Tokyo) Full Record
   6th - 10th November 1978

NEACRP-A- 355
   Interim Progress Report on the NEA Data Bank:
   (also numbered SEN/DATA (79)5 and NEANDC 119'A')

NEACRP-A- 356
   Power peaking and its design margin of JOYO
   F. Yoshino

NEACRP-A- 357
   A study on the potential safety advantage of heterogeneous LMFBRs (I)
   K. Miyagi et Al.

NEACRP-A- 358
   Some correlations between isotopes of Nd, U, Pu and burnup parameters for the FBR irradiated fuel
   S. Nakayama et Al.

NEACRP-A- 359
   Criticality computation using the Monte-Carlo Code KENO-4 with a new multi-group constants library
   Y. Naito et AL.

NEACRP-A- 360
   Report to the NEA Nuclear Data Committee September 1979 Sub-committee on technical activities of the NEANDC

NEACRP-A- 361
   Summary of NEACRP views on actinide production and burn-up
   J. Hirota et Al.

NEACRP-A- 362
   Statement from Dr. Chrien (NEANDC): Exchange of evaluated nuclear data files between NEA Member countries

NEACRP-A- 363
   Report on the 21st Meeting of NEANDC by the NEACRP observer
   J. Debrue

NEACRP-A- 364
   Investigations related to the international comparison calculations of a large sodium-cooled fast breeder reactor
   C. Broeders
   1979

NEACRP-A- 365
   Experimental evidence of isotopic correlations
   L. Koch

NEACRP-A- 366
   Isotopic correlation techniques - A review.
   H. Kuesters, M. Marzo

NEACRP-A- 367
   Kinetic Benchmark
   H. Kuesters
   Munich 1975

NEACRP-A- 368
   NEACRP Specialists Meeting on 3-dimensional rating distributions in operating reactors. Proposed participants at 27.9.79.

NEACRP-A- 369
   Critical experiments in a zero-power fast reactor lattice with breeder zones of thorium and uranium (EIR)
   U. Schmocker et Al.

NEACRP-A- 370
   Calculation of the multiplication factor of a PWR spent fuel storage configuration
   G. Minsart

NEACRP-A- 371
   Requirements for fission-product nuclear data related with reactor fuel characterization
   L. Leenders et Al.

NEACRP-A- 372
   "Burnotheque" A valuable standard for accurate burn-up determination by non-destructive examination
   H. Adachi, J. Basselier, L. Leenders

NEACRP-A- 373
   NEACRP monograph: "Current status of fast reactor physics" Reactor coefficients
   Argonne National Laboratory

NEACRP-A- 374
   Fast reactor fuel cycle studies
   Y.I. Chang, C.E. Till

NEACRP-A- 375
   Analysis of radial fission rate distributions in ZPPR cores (ANL)
   P.J. Collins

NEACRP-A- 376
   LMFBR reactivity surveillance using ex-core detectors
   M.J. Lineberry, S.G. Carpenter, C.L. Beck

NEACRP-A- 377
   Isotope correlations and measurements in the U.S.
   P.J. Persiani

NEACRP-A- 378
   Experimental studies of 350 MW(e) Heterogeneous LMFBR cores at ZPPR
   P.J. Collins et Al.

NEACRP-A- 379
   Experimental studies of large conventional LMFBR cores at ZPPR
   M.J. Lineberry et Al.

NEACRP-A- 380
   Neutronic problems related to the heterogeneous core concept safety: studies devoted to the sodium effect
   J.C. Cabrillat, P. Hammer

NEACRP-A- 381
   Actinide cross-sections averaged using the ANL central spectrum for the NEACRP LMFBR benchmark model

NEACRP-A- 382
   Definition des caracteristiques d'un milieu de reference a combustible oxyde d'uranium enrichi et A K = 1 a partir des mesures realisees au CEA
   J. Bouchard, M. Darrouzet, L. Martin Deidier

NEACRP-A- 383
   Comments on the draft Proceedings of the NEACRP/IAEA Specialists Meeting on the international comparison calculation of a large sodium-cooled fast breeder reactor
   M. Nakagawa

NEACRP-A- 384
   Proposal for the third specialists meeting on reactor noise (SMORN III)
   - submission to NEACRP 22nd meeting
   Y. Kuroda et AL.

NEACRP-A- 385
   Notes on U.S. Fast Reactor Blanket and Shield interface studies

NEACRP-A- 386
   Isotopic correlations in irradiated nuclear fuels (Euratom Ispra)
   C. Foggi

NEACRP-A- 387
   A simple comparison of adjusted data sets for iron-based on measurements in ASPIS and in the cores of fast reactor criticals
   M.C.G. Hall

NEACRP-A- 388
   Preliminary version of the EURLIB variance-co-variance matrices
   M.C.G. Hall

NEACRP-A- 389
   Contribution to the IAEA/NEA Programme of uncertainty analyses in generic reactors - A sodium-cooled fast reactor
   M.C.G. Hall

NEACRP-A- 390
   Out-of-Pile critically studies (US)

NEACRP-A- 391
   standardized safety analysis of nuclear fuel shipping containers Robert M. Westfall and Leslie M. Petrie

NEACRP-A- 392
   Progress Report of the Dutch Nuclear Data project for fast reactors covering the period April 78/ Sept. 79

NEACRP-A- 393
   The investigation of control rod physics problems in the large power  fast reactor mock-up
   Y.A. Kasanskii et Al.

NEACRP-A- 394
   Nuclear data and precisions of actinide build-up calculation in fast  reactors
   O.D. Bakumenko et Al.

NEACRP-A- 395
   Benchmark experiments related to actinide production in thermal reactors: Experiments in the VENUS critical facility (SCK/CEN, Mol.)
   De. Raedt, Leenders, Minsart,

NEACRP-A- 396
   Summary Record of 22nd Meeting of the Committee (Paris)
   1st - 5th October 1979

NEACRP-A- 397
   Official Summary Record of the 22nd Meeting of the Committee (Paris)
   1st - 5th October 1979

NEACRP-A- 398
   Information Sheet - Call for Papers: "Specialist Meeting on Nuclear Data and Benchmarks for Reactor Shielding (Paris)
   27th - 29th October 1980

NEACRP-A- 399
   Report by Dr. E. Fort on the 22nd Meeting of NEACRP to the NEANDC

NEACRP-A- 400
   An assessment of the Accuracy Requirements on Higher Actinide Nuclear Data for Fast Reactors
   B.H. Patrick, M.G. Sowerby

NEACRP-A- 401
   CSNI/NEACRP Standard Problem Exercise on Criticality Codes for Spent Fuel  Transport Containers

NEACRP-A- 402
   NEA Data Bank Activity Report

NEACRP-A- 403
   Progress Report on Belgian Contribution to the USNRC Neutron Transport Theory Blind Test in a LWR Pressure Vessel Benchmark
   A. Fabry

NEACRP-A- 404
   Information Sheet for SMORN III

NEACRP-A- 405
   Integral Studies of Fast Reactor Component Activation in ZEBRA
   J.E. Sanders, W.H. Taylor

NEACRP-A- 406
   Experimental Study of Structural Materials Capture in Fast Breeder Spectra
   M. Darrouzet, F. Lyon, G. Rimpault, L. Martin Deidier

NEACRP-A- 407
   Note on ENDF/B Structural Data
   P.F. Rose, M. Divadeenam, A. Prince

NEACRP-A- 408
   Measurements and Calculations for the 235U/Fe Benchmark Assembly on ZPR-9
   R.D. McKnight, D.C. Cade

NEACRP-A- 409
   Winfrith Experiment of RETRAN for PWR Pressurized Transients with Particular Emphasis on ATWS
   S.R. Kinnersly

NEACRP-A- 410
   Pressurized Transient Studies
   B.A. Zolotar

NEACRP-A- 411
   Further Studies of Heterogeneity Problems of Plate and Pin Cells in ZEBRA
   J.M. Stevenson

NEACRP-A- 412
   Some Problems Related to the Small Zone Experiment Analysis
   A.Santamarina

NEACRP-A- 413
   Recent Developments in Predicting Sodium Void Reactivities
   C.L. Beck, M.J. Lineberry

NEACRP-A- 414
   ZPPR Studies of Control Rod Worths in Large Homogeneous LMFBRs
   H.F. McFarlane, P.J. Collins, G.L. Grasseschi, H.A. Harper

NEACRP-A- 415
   Experiment Studies of 6000-Litre LMFBR Cores at ZPPR
   S.G. Carpenter, P.J. Collins, C.L. Beck, J.M. Gasidlo, R.W. Goin, R.E. Kaiser, D.W. Maddison, D.N. Olsen

NEACRP-A- 416
   A Comparison of Effective Beta Measurements on Plutonium- and Uranium-Fueled Fast Critical Asemblies
   E.F. Bennett

NEACRP-A- 417
   Utilization of Information from Operating Reactor JOYO
   S. Tamura

NEACRP-A- 418
   A Review of the Principles of Correlation Procedures and the Delilah Method of Correlation, with Application to the Winfrith SGHW Reactor
   A.N. Buckler

NEACRP-A- 419
   Reactivity Balance Meter: Feed-Back Effects Measurements at Phenix
   J.C. Gauthier

NEACRP-A- 420
   Measurement of Doppler and Thermal Exchange Coefficients in a PWR by Analyzing the Dynamic Response After a Rod Drop
   P. Bernard

NEACRP-A- 421
   Experience-to-Theory Feedback in the Development and Application of core Performance Evaluation Methods
   S. Felici, P. Peroni

NEACRP-A- 422
   Special Tests at CAORSO Start-up for BWR Simulator Methods Verification
   S. Grifoni

NEACRP-A- 423
   Methods of Utilization of Information from Operating Reactors
   B.A. Zolotar

NEACRP-A- 424
   The Analysis by Several Neutron Transport Methods of a Small PWR Model Problem
   M.J. Halsall

NEACRP-A- 425
   Summary of the Second Technical Meeting on the Nuclear Transmutation of Actinides
   W. Hage

NEACRP-A- 426
   Application of Sensitivities to Actinide Build-up Problems
   J.C. Estiot, G. Palmiotti, M. Salvatores

NEACRP-A- 427
   A Survey of IWGRRM Activities
   R. Martinelli

NEACRP-A- 428
   Treatment of Internal Rectangular Voids in diffusion Theory
   E.M. Gelbard, R.M. Lell, C.H. Adams

NEACRP-A- 429
   Preliminary Neutronic Studies of the Compatibility Problems Between the Heterogeneous and Homogeneous Core
   J.C. Cabrillat

NEACRP-A- 430
   Flux Tilting in Fast Reactor Systems: Considerations of System Geometry and Composition on Eigenvalue Separation
   Y. Orechwa

NEACRP-A- 431
   Neutronic and Thermal-Hydraulic Space-Time Effects in Large Homogeneous and Heterogeneous LMFBRs
   Y. Orechwa

NEACRP-A- 432
   A Study on the Potential Safety Advantage of Heterogeneous LMFBRs (II)
   K. Miyagi, H. Laziwara, I. Komatsu, K. Susuki, K. Aoki, I. Ohtake, T. Inoue, T. Yokoyama

NEACRP-A- 433
   Blanket studies at CEA: Status of the Art
   M. Salvatores

NEACRP-A- 434
   Core instrumentation
   B.A. Zolotar

NEACRP-A- 435
   Notes on out-of-pile criticality problems
   P. Hemming

NEACRP-A- 436
   Framework of reactor noise analysis benchmark tests for SMORN III
   Japanese Preparatory Committee of SMORN III

NEACRP-A- 437
   Nuclear Data Needs for the analysis of generation and burn-up of actinide  isotopes in nuclear reactors
   H. Kuesters

NEACRP-A- 438
   Comments on the draft Proceedings of the NEACRP/IAEA Meeting on International Comparison Calculations
   R.D. McKnight

NEACRP-A- 439
   Summary Record of 23rd Meeting held at Argonne National Laboratory,
   Idaho Falls (22nd-26th Sept. 1980) also listed as SEN/NEACRP/M(80)1

NEACRP-A- 440
   Summary Record (OFFICIAL VERSION) of 23rd Meeting of the Committee,
   Argonne Nat. Lab. (Idaho Falls)
   22nd - 26th Sept. 1980

NEACRP-A- 441
   CSNI/NEACRP A Standard problems exercise on criticality codes for spent fuel transport containers,   1981

NEACRP-A- 442
   Summary record of NEACRP ad hoc working group meeting on evaluation co-ordination

NEACRP-A- 443
   Summary record of second NEACRP ad hoc working group meeting on evaluation co-ordination

NEACRP-A- 444
   Participation from and request data for Specialists Meeting on Fast Neutron Scattering on Actinide Nuclei 23/25 Nov. 81
   (also as NEANDC-A-147)

NEACRP-A- 445
   Description of the Pin and Plate Geometry Cadenza assemblies for the international comparison of calculations
   J.M. Stevenson, J.L. Rowlands

NEACRP-A- 446
   NEA Data Bank Activity Report

NEACRP-A- 447
   Proposed International Comparison Calculation of Fast Reactor Critical  Assemblies in Pin and Plate Geometries

NEACRP-A- 448
   High Priority Nuclear Data Measurement Requirements

NEACRP-A- 449
   Summary Report of 22nd NEANDC Meeting

NEACRP-A- 450
   Heterogeneity Effects in MASURCA Rodlet Cells

NEACRP-A- 451
   Sodium Void Reactivity Worths in Plate and Pin Cell Assemblies

NEACRP-A- 452
   On the Geometric Modelling Effects for the Pin/Plate Heterogeneity
   Calculation

NEACRP-A- 453
   Validation Results for the SDX Cell Homogenization code for Pin Geometry

NEACRP-A- 454
   Space and Angle Finite Element Method for Solving Three-Dimensional Multi-Group Neutron Transport Problems

NEACRP-A- 455
   Reactor Noise Analysis Benchmark Exercise in Connection with SMORN-III

NEACRP-A- 456
   Status of 3D Transport Calculations for Reactors

NEACRP-A- 457
   Perturbation Methods for Cutting Costs of Transport Calculations

NEACRP-A- 458
   Tracasyn: A 3D Power Distribution Evaluation Using a Multi-Channel Synthesis Method from the Results of 2D Transport Calculations

NEACRP-A- 459
   The Solution of the Multigroup Neutron Transport Equation Using Spherical Harmonics

NEACRP-A- 460
   Specifications for a LWR Benchmark Problem with Adjacent Poisoned Fuel Rods

NEACRP-A- 461
   ANL Calculations of the NEACRP LMFBR Depletion Benchmark Problem

NEACRP-A- 462
   Measurements of Fission Products Decay Heat for Fast Neutron Fissions

NEACRP-A- 463
   Decay Heat Measurements and Criticality Control of Irradiated LWR-Fuel
   Elements

NEACRP-A- 464
   Beta and Gamma Decay-Heat Measurements for Fast and Thermal Reactors,
   Particularly for Pu-239

NEACRP-A- 465
   Fission product Decay Heat from U235 and Pu239 - A Brief Survey of the
   Experimental and Theoretical Data

NEACRP-A- 466
   Decay Heat in Fast Power Reactors: Objectives, Qualifying the Computer
   Code

NEACRP-A- 467
   Out-of-Pile Subcriticality Monitoring

NEACRP-A- 468
   The Qualification of Nuclear Data and Methods for Post-Irradiation Analysis and Application of Isotopic Correlation Techniques to Nuclear Safeguards

NEACRP-A- 469
   Nuclear Material Safeguards Surveillance and Accountancy by Isotope Correlation Techniques

NEACRP-A- 470
   Recent Development in 238U Capture Measurements

NEACRP-A- 471
   Delayed Neutron Data

NEACRP-A- 472
   An Analytical Study on Uncertainties of Reactivity Scale (Beta,eff) of Large LMFBR Cores

NEACRP-A- 473
   The Reactivity Scale for Fast Spectrum Criticals

NEACRP-A- 474
   RETRAN Validation: Analysis of the LOFT L6-5 Experiment

NEACRP-A- 475
   The SPLOSH/SMASH Averaging Problem

NEACRP-A- 476
   A Preliminary Study of a Method of Spatial Averaging for SPLOSH

NEACRP-A- 477
   Further Aspects of the Spatial Averaging Problem

NEACRP-A- 478
   Transient Effect on Reactivity in Reactor Point Kinetics Calculation

NEACRP-A- 479
   Measurement of Doppler and Heat Transfer Coefficients in PWR

NEACRP-A- 480
   Measurements and Calculations of the Fuel Temperature Coefficient of
   Reactivity for Hinkley Point 'B' AGR

NEACRP-A- 481
   Measurements of the Doppler Effect at Phenix

NEACRP-A- 482
   Measured and Calculated Pin Power Distributions in the DODEWAARD BWR

NEACRP-A- 483
   Refuelling Analysis of Pin-Fuelled HWR-FUGEN

NEACRP-A- 484
   A Study on the Safety and Physics Aspects of Large Heterogeneous LMFBR's

NEACRP-A- 485
   Effects of Cell Asymmetry on the Performance of a Large Heterogeneous
   Critical Assembly

NEACRP-A- 486
   Control Rod Experiments in RACINE

NEACRP-A- 487
   Recent Developments in Heterogeneous Core Critical Experiments in the
U.S.

NEACRP-A- 488
   Progress in the U.K. Analysis of the BIZET Heterogeneous Fast Reactor
   Assemblies.

NEACRP-A- 489
   On the relationship between Local Flux Tilt and Eigenvalue Separation during delayed Critical Transients in a Fast Reactor.

NEACRP-A- 490
   The effects of Intra-Cell Adjoint Flux Heterogeneity on FOP Reactivity Calculations.

NEACRP-A- 491
   Sixth International Conference on Radiation Shielding.

NEACRP-A- 492
   Summary Record (full minutes) of the Twenty-Fourth Meeting of NEACRP.

NEACRP-A- 493
   NEA Summary Record of the 24th Meeting of NEACRP.

NEACRP-A- 494
   Proceedings of SMORN III.
    Pergamon Press
   1982
  
NEACRP-A- 495
   Summary Record of 3rd NEACRP ad hoc Working Group Meeting on Evaluation Coordination, Winfrith, November 1981.
    Also as NEANDC 150A

NEACRP-A- 496
   Information sheet on Restricted Specialists Meeting on the NEACRP Benchmark Calculations for fuel burn-up on LMFBR -
   April 1982, Cadarache.

NEACRP-A- 497
   Information sheet on Restricted Specialists Meeting on Shielding Benchmark Calculations, 1st/2nd July 1982, Paris.

NEACRP-A- 498
   The Winfrith Iron Benchmark Experiment.
    M.D. Carter, A.K. McCracken and A. Packwood

NEACRP-A- 499
   Summary record of first meeting of Scientific Coordinating Group of JEF Project.
    Also NEANDC 154A

NEACRP-A- 500
   High Priority Nuclear Data Measurement Requirements for the Reactor Programme.
    Also NEANDC 156A

NEACRP-A- 501
   Fast breeder reactor shielding benchmark results.

NEACRP-A- 502
   NEA Data Bank Activity Report, September 1982.

NEACRP-A- 503
   Draft proceedings of the NEACRP Specialists' Meeting on LMFBR Shielding  Benchmark, Paris, 1-2 July 1982.

NEACRP-A- 504
   Proceedings of the NEACRP Specialists' Meeting on the "NEACRP LMFBR Benchmark Calculation Intercomparison for Fuel Burn-Up",
  Cadarache, 28th to 30th April, 1982.
    G. Palmiotti and M. Salvatores

NEACRP-A- 505
   Integral Shielding Benchmarks: Status of the EURACOS Iron and sodium deep penetration experiments JRC, Ispra.
    H. Rief

NEACRP-A- 506
   Draft PWR shielding benchmark calculation.
    G. Hehn

NEACRP-A- 507
   Fast neutron flux measurements with the 93Nd(n,n') reaction - Brief  review of the SCK/CEN activities in this field.
    H. Tourwe

NEACRP-A- 508
   Interlaboratory comparison of fluence neutron dosimeters in the frame of the PSF start-up measurement programme.
    H. Tourwe, F. Kann, A. Fudge, W.L. Zijp, W. Mannhart and A. Thomas

NEACRP-A- 509
   Standardisation and Portability. Activities September 1981 to August 1982 -
   NEA Data bank.

NEACRP-A- 510
   The FMS Treatment of Gadolinium Burnable Poison in Light Water Reactors.
    H.K. Naess, T. Skardhamar

NEACRP-A- 511
   Bizet programme; analysis of subcritical rod worth measurements in the single annular core BZD/2.
    H. Giese, T. Skardhamar

NEACRP-A- 512
   Control-rod calculation methods and uncertainties for a power LMFBR design.
    C. Giacommetti, G. Humbert, G. Palmiotti and M. Salvatores.

NEACRP-A- 513
   Homogenization method of pin rods in ZPPR-10A assembly.
    T. Takeda, K. Tanimoto and T. Yamamoto.

NEACRP-A- 514
   Fast Reactor Control Rod Calculation Methods and Validation Experiments.
    J.L. Rowlands and M.J. Grimstone

NEACRP-A- 515
   Calculation methods for control rods in LMFBR's.
    H.F. MacFarlane and P.J. Collins

NEACRP-A- 516
   A control absorber rod in Phenix: comparison of calculated and measured worth.
    G. Humbert, R. Petiot and P. Coulon

NEACRP-A- 517
   Critical experiments of the reactor physics of distorted cores.
    F. Helm and G. Henneges

NEACRP-A- 518
   Reactor physics modelling of distorted cores.
    W. Maschek

NEACRP-A- 519
   Analysis of Fuel slumping experiment on FCA Assembly VIII-2.
    M. Nakano and H.Tsunoda

NEACRP-A- 520
   Effect of cell calculation model on the analysis of fuel slumping experiment.
    E. Wachi, T. Takeda and T. Sekiya

NEACRP-A- 521
   Burn-up calculations for a BWR Lattice with Adjacent Poisoned Fuel Rods.
    C. Maeder and P. Wydler

NEACRP-A- 522
   Monk 6.1 Validation.
    G. Walker and R.J. Brissenden.

NEACRP-A- 523
   General Considerations on physics and technical aspects for storage reprocessing, and for shipment of reactor fuel.
    H. Kuesters.

NEACRP-A- 524
   The CRISTO III Experiment.
    A. Santamarina and B. Nouveau.

NEACRP-A- 525
   A study on a nuclear criticality safety evaluation technique.
    Y. Naito, J. Kata Kura and M. Tokota

NEACRP-A- 526
   Parametric reactivity study of compact PWR fuel storages including fuel burnup effect.
    G. Minsart

NEACRP-A- 527
   Evaluation of computational models for spallation and fission reactions used in an accelerator breeding and transmutation analysis code.
    Y. Nakahara.

NEACRP-A- 528
   Some new approaches to the efficient solution of the transport equation.
    C. Budd

NEACRP-A- 529
   Monte Carlo Calculations of the WSGHWR using the group data version of Monk.
    J.L. Hutton, P.B. Kemshell and K. Robichaud

NEACRP-A- 530
   Group collapsing strategy for 3-D design calculations.
    M. Cosimi, C. Giaccometti, G. Palmiotti and M. Salvatores

NEACRP-A- 531
   Recent developments and improvements in the code system for the neutronic design of fast breeder reactors at CEA.
    C. Giacometti, J.C. Estiot, G. Palmiotti, C. Grondein, G. Le Cardinal, M. Ravier.

NEACRP-A- 532
   Iterative Solution of the DFEM Algorithm of the Three Dimensional Neutron Transport Problems.
    T. Fujimara, Y. Nakahara, M. Matsumura.

NEACRP-A- 533
   BETA and Gamma-ray decay energy from fragments from the fission of U235 and Pu 239 in a fast reactor.
    W.H. Taylor, M.F. Murphy, M.R. March.

NEACRP-A- 534
   A brief survey of experimental and theoretical data on fission produce decay heat from U235 and Pu239.
    M.F. James

NEACRP-A- 535
   Informal Memorandum on fast reactor short-term fission product decay heat and its uncertainty.
    R.W. Peelle, J.K. Dickens

NEACRP-A- 536
   Measurements of Gamma-ray energy release rates following fast-neutron fissions of U238, Th232 and natural uranium.
    M. Akiyama, S. An

NEACRP-A- 537
   Isotope correlations for safeguards surveillance and accountancy methods.
    P.J. Persiani, Kalimollah

NEACRP-A- 538
   Subcriticality monitoring by means of the pulsed neutron technique.  Measurements on single PWR-type sub-assemblies.
    J. Debrue

NEACRP-A- 539
   Applications of calculated isotope correlations in the determination of the input balance at the La Hague reprocessing plant.
    A. Giacometti, R. Girieud

NEACRP-A- 540
   Comparison of measured neutron reaction rates in fast reactor steels with values calculated using FD5 Data.
    M.F. Murphy, J.M. Stevenson, W.H. Taylor

NEACRP-A- 541
   The importance of electron transport in reactor heating calculations.
    A.D Knipe

NEACRP-A- 542
   ANL/AEEW Comparison of reaction-rate ratio techniques in ZEBRA.
    D.W. Maddison, G. Ingram

NEACRP-A- 543
   A comparison of central reactor-rate ratio measurement techniques in BIZET cores.
    B. Bohme, B.L.H. Burbidge

NEACRP-A- 544
   A comparison of counting and mass spectrometer methods for measuring U238 capture.
    J.M. Gasidlo, D.W. Maddison, R.T. Armani, J.A. Morman, S.G. Carpenter

NEACRP-A- 545
   On the Reactivity Scale for large LMFBR cores.
    H. Nakamura, N.Tsugi

NEACRP-A- 546
   Recent developments in small sample worths.
    K.S. Smith, R.W. Schaefer

NEACRP-A- 547
   Benchmark intercomparisons of reactivity worths in an LMFBR-type plate critical assembly.
    L.G. LeSage

NEACRP-A- 548
   Comparison of reactivity scales based on Kinetics measurements and Plutonium fuel worths in eleven ZEBRA assemblies.
    J.M. Stevenson

NEACRP-A- 549
   Gamma heating measurements in a heterogeneous core configuration.
    D. Calamand

NEACRP-A- 550
   Sodium-void reactivity in a heterogeneous LMFBR.
    H.F. McFarlane, C.L. Beck, H. Henryson II

NEACRP-A- 551
   U.S. Fast critical assembly developments.
    M.J. Lineberry

NEACRP-A- 552
   Physics assessments of LMFBR integral parameters.
    M.J. Lineberry, H.F. McFarlane, P.J. Collins

NEACRP-A- 553
   Note in CSNI Activities on Nuclear Criticality Safety Computations.
    R.W. Peelle

NEACRP-A- 554
   Draft Notes on the Reduced Enrichment Research and Test Reactor (RERTR) Program.
    L.G. LeSage

NEACRP-A- 555
   Investigation of physical characteristics during the BN-600 Reactor start-up.
    Y.A. Kazanski et al.

NEACRP-A- 556
   A Study on shielding calculation technique using the Albedo-SN method.
    M. Kawai, J. Itoh

NEACRP-A- 557
   The Third Specialists' Meeting on Reactor Noise - A Brief Overview.
    J. Hirota, Y. Shinohara

NEACRP-A- 558
   Summary Record of the Second Meeting of the Scientific Co-ordinating Group,
   Antwerp 8th Sept. 1982.
    Also NEANDC-A-162

NEACRP-A- 559
   Summary Record of 25th Meeting of NEACRP, Karlsruhe, September 1982
   (SEN/NEACRP/M(82)1).

NEACRP-A- 560
   Full minutes of 25th Meeting of NEACRP Committee, Karlsruhe, September 1982.
    Also NEANDC-171A

NEACRP-A- 561
   List of NEACRP documents A and L categories.

NEACRP-A- 562
   Summary Record of 23rd Meeting of NEANDC, 27th Sept./1st Oct. 1982.
   (NEANDC-172'A')

NEACRP-A- 563
   Summary Record of 23rd Meeting of NEANDC.
    Also NEANDC-A-174, (SEN/NEANDC/M(82)1).

NEACRP-A- 564
   Critical assembly descriptions.
    B. Richmond
    1983
   
NEACRP-A- 565
   Summary Record of the Third JEF Meeting.
    Also as NEANDC 175 A

NEACRP-A- 566
   Summary record of the 4th meeting of the Scientific Coordinating Group of the  JEF project.
    Also NEACRP-566-A

NEACRP-A- 567
   Benchmark on Interactive Effects of Gd-poisoned pins in BWRs, status report.
    C. Maeder, P. Wydler

NEACRP-A- 568
   High Priority Nuclear Data Measurement Requirements for the Reactor Programme
   (Sept. 83).
    Also NEANDC-180-A

NEACRP-A- 569
   Summary Record of 26th NEACRP Meeting, Oak Ridge, USA, 17th - 21st October 1983
    Also as SEN/NEACRP/M(83)1 and NEANDC-180-A

NEACRP-A- 570
   Summary Record (official) of 26th NEACRP Meeting, OakRidge, USA, 17th - 21st October 1983.
    Also as NEANDC-A-181

NEACRP-A- 572
   NEANDC Activity Report.

NEACRP-A- 573
   MAGIK. A Computer Program to Investigate Transients in AGR and MAGNOX Reactors.
    J.K. Fletcher and M.A. Perks.

NEACRP-A- 574
   Ejected Rod Calculation, Kinetic Axial Modelisation.
    R. Renain

NEACRP-A- 575
   Power Distribution Prediction for a Large Commercial LMFBR.
    R. De Wouters and G. Flamenbaum

NEACRP-A- 576
   Perturbation Methods for Power Distribution Prediction.
    G. Palmiotti and M. Salvatores

NEACRP-A- 577
   The Effects of Simplified Control Rod Modelling on Neutronics Calculations for the Prototype Fast Reactor.
    D.J. Lord and T.D. Newton

NEACRP-A- 578
   The Prediction of Sub-Assembly Powers Throughout the Fuel Cycle of a Commercial  Fast Reactor.
    R.E. Sunderland

NEACRP-A- 579
   Radial Dependence of C/E Value in JUPITER-I Core Analysis
    Y. Kato, M. Yamamoto, K. Shirakata and T. Takeda

NEACRP-A- 580
   ZPPR Data Relevant to the Prediction of Power Distribution in Large LMFBRs through the Burnup Cycle.
    P.J. Collins

NEACRP-A- 581
   Thermo Hydraulic Transient Simulation of LMFBRs using COMMIX-1A Computer Code.
    W.L. Baumann, W.T. Sha and H.M. Domanus

NEACRP-A- 582
   IFAC Workshop - Modelling and Control of Electric Power Plants.

NEACRP-A- 583
   SALAMANDRE: A Digital Simulator for Light Water Pressurised Reactors.
    P. Bernard, C. Bonnet, J. Chinardet, F. Ducamp, S. Nisan,  J. Romeyer-Dherbery

NEACRP-A- 584
   LWHCR Moderator-Voilage Experiments.
    R. Chawla, K. Gmuer, H. Hazel and R. Seiler

NEACRP-A- 585
   Recycling of Uranium-236.
    J.R. Askew

NEACRP-A- 586
   The Trend Neutronics Studies concerning the Uranium Recycle.
    C. Golinelli

NEACRP-A- 587
   Technical and Economic Aspects of Plutonium Recycling.
    O. Beer and P. Schmiedel

NEACRP-A- 588
   Investigations on a Tight Lattice PWR in the Federal Republic of  Germany.
    H. Kuesters

NEACRP-A- 589
   The Superposition Method, A New Approach to Pin Power Determination.
    F. Nissen

NEACRP-A- 590
   Comparison of Pin Powers in Thermal Reactors Calculated from Coarse Mesh Methods.
    M. Hamasahi, W. Kawamura and T. Takeda

NEACRP-A- 591
   Distributed Heating Calculations for a Fast Reactor Application to the PFR Equilibrium Core Model.
    G. Reddell and A.T.D. Butland

NEACRP-A- 592
   The MONK Code and its Validation from Data.
    P. Hoge, G. Walker, R.J. Brissenden and D.E. Bendall

NEACRP-A- 593
   New Developments on the Critical Eigenvalue Assessment.
    R.D. McKnight

NEACRP-A- 594
   TRIMARAN: A Three Dimensional Multigroup P1 Monte Carlo Code for Criticality Studies.
    G. Erment

NEACRP-A- 595
   Status of CSNI Working Group on Standard Problem Exercises on Criticality Calculations for Spent Fuel Transport Casks and Arrays of Fissile Material Packages.
    G.E. Whitesides

NEACRP-A- 596
   Difficulties with Experiments Involving Arrays of Fissile Solutions.
    J.T. Thomas

NEACRP-A- 597
   Generalised Monte Carlo Perturbation Algorithms for Correlated Sampling and a Second Order Taylor Series Approach.
    H. Rief

NEACRP-A- 598
   Monte Carlo Depletion Calculation in a Slab.
    A.F. Course, M.J. Halsall and J.L. Hutton

NEACRP-A- 599
   Production of Fissile Material.
    D.E. Bartine and J.O. Johnson
    Comments on Out-of-Pile.

NEACRP-A- 600
   The LOTUS Fusion-Fission Hybrid Project.
    L. Green, P.A. Maldy, A. Kumar, C. Sahraoui and K. Gmiir

NEACRP-A- 601
   Measurements of Reactor Rates in and Around Control Rods at ZPPR.
    P.J. Collins

NEACRP-A- 602
   A Homogenisation Method of Control Rods with Neutron Leakage Effect.
    S. Ono and T. Takeda

NEACRP-A- 603
   Boron Capture in Boron Carbide Rodlets Irradiated in PHENIX: An Experiment to Calculation Comparison.
    G. Humbert, G. Palmiotti and C. Tourni

NEACRP-A- 604
   A Sensitivity Approach to Study Control Rod Worth Uncertainties.
    G. Palmiotti and M. Salvatores

NEACRP-A- 605
   Control Rod Worths and Interactions in Fast Reactors.
    H. Grese

NEACRP-A- 606
   Parametric Studies for the Heterogeneous Core Concept in the Framework of the PRERACINE and RACINE Experimental Programs.
    G. Humbert, K. Kappler, M. Martini, G. Norvez, G. Rimpault, B. Ruelle,
   W. Scholtyssek and A. Stanculescu

NEACRP-A- 607
   Validation of Neutronic Calculations for Distorted Core Configurations arising in Accident Situations of LMFBRs.
    H. Kuesters

NEACRP-A- 608
   Reactivity Effects of Fuel Rearrangement in Fast Reactor Rod Bundles.
    F. Helm and G. Henneges

NEACRP-A- 609
   Measurements and Computation of the Reactivity Effects of Accident-Caused Core Distortions in Liquid Metal Fast Breeder Reactors.
    F. Helm, G. Henneges and W. Maschek

NEACRP-A- 610
   Intercomparison of Reaction Rate Measurement Techniques in MASURCA.
    W. Scholtyssek

NEACRP-A- 611
   Intercomparison of Reaction Rate Measurement on Fast Reactors.
    D.W. Maddison and S.G. Carpenter

NEACRP-A- 612
   The Present Accuracy of Physics Characteristics of Unirradiated Fast Reactor Cores.
    H. Kuesters and S. Pilate

NEACRP-A- 613
   Summary of the Meeting "Status of Static Reactor Calculations in Nordic Countries".
    S.-O. Lindahl

NEACRP-A- 614
   Progress Report on the International Comparison of Calculations for the CADENZA Assemblies (the Pin-Plate Benchmark).
    M.J. Grimstone, J.L. Rowlands and J.M. Stevenson

NEACRP-A- 615
   ANL, Intercomparison of Cell Heterogeneity Effects in Pin and Plate Geometries.

NEACRP-A- 616
   Collision Probabilities for Plate Geometry Cells with an Approximate Treatment of Plate Edge Regions.
    M.J. Grimstone and J.L. Rowlands

NEACRP-A- 617
   A Method of Calculating Collision Probabilities for the Pin Cell Minicalandrier used in Fast Reactor Critical Facilities.
    M.J. Grimstone and J.L. Rowlands

NEACRP-A- 618
   Results of the NEA PWR Shielding Benchmark.
    G. Hehn

NEACRP-A- 619
   Adjustment of Neutron Multigroup Cross-sections.
    G. Helm, R.-D. Baechle, G. Pfister and M. Mattes, G. Hehn

NEACRP-A- 620
   The Sixth International Conference on Radiation Shielding, A Brief Overview.
    T. Asaoka, T. Lloyds, T. Suzuki and S. Kikuchi

NEACRP-A- 621
   Experimental Studies of Radially-Heterogeneous LMFBR Critical Assemblies a ZPPR.
    H.F. McFarlane, S.G. Carpenter, P.J. Collins, D.N. Olsen and S.B. Brumbach

NEACRP-A- 622
   Recent Developments in the Control Worth Discrepancy
    K.S. Smith and R.W. Schaefer

NEACRP-A- 623
   NEACRP Reactivity Benchmark Proposal.
    L.G. LeSage

NEACRP-A- 624
   Overview of the Specialists' Meeting on In-Core Instrumentation and the Assessment of Reactor Nuclear and Thermal/Hydraulic Performance,
   Fredrikstad (Norway), 10-13 October, 1983.
    R. Martinelli

NEACRP-A- 625
   Summary Record of the Fifth Meeting of the Scientific Coordination Group of the Joint Evaluated File Project.
    Also JEF/DOC-58 with annexes, and NEANDC-A-183 without annexes

NEACRP-A- 626
   Summary Record of the 24th Meeting of the NEANDC held in Tokai-Mura, Japan,
   12th-16th March 1984.
    Also NEANDC-A-194, (SEN/NEANDC/M(84)1)

NEACRP-A- 627
   Sensitivity Analysis and Monte Carlo - the DATAK Code.
    M. Armishaw, A.K. McCracken, P.C. Miller

NEACRP-A- 628
   The Winfrith Water Benchmark Experiment.
    M.D. Carter, A. Packwood

NEACRP-A- 629
   Results and Calculational Model of the Winfrith Iron Benchmark Experiment.
    J. Butler, M.D. Carter, A.K. McCracken, A. Packwood

NEACRP-A- 630
   The ASPIS Graphite Benchmark Experiment: Part 1 Experimental Data and Preliminary Calculations.
    M.D. Carter, P.C. Miller, A. Packwood

NEACRP-A- 631
   Summary Record (Official minutes) of the 24th Meeting of the NEANDC held in Tokai-Mura, Japan, 12th -26th March 1984.
    Also as NEANDC-195"A"

NEACRP-A- 632
   NEA Specialists' Meeting on Shielding Benchmark, Saclay, 10th November 1984.

NEACRP-A- 633
   NEA Data Bank Activity Report, October 1984.

NEACRP-A- 634
   Report by the NEA Secretariat on Recent Activities of the Committee on the Safety of Nuclear Installations of Interest to the Committee on Reactor Physics.
   SINDOC (84)232.

NEACRP-A- 635
   The CEA Experimental Program for Validating the Tight Lattice Reactor Concept

NEACRP-A- 636
   Further Investigations in the PROTEUS-LWHCR Phase I Program,
   R. Chawla, K. Gmuer, H. Hager, R. Seiler.

NEACRP-A- 637
   Physics Problems on Analysis of High Conversion Pressurized Water Reactor (HCPWR) with Tighter Pitch Lattices (An Analysis of PROTEUS-LWHCR Cores by SRAC System).
   Yukio Ishiguro, Keichiro Tsuchihashi and Makoto Sasaki.

NEACRP-A- 638
   Studies of Pu Recycling in Close-Packed PWR Lattices,
   Erik Johansson.

NEACRP-A- 639
   Analysis of FCA Assembly X using Monte Carlo and Deterministic Method,
   S. Iijima, M. Nakagawa.

NEACRP-A- 640
   Prediction of K-effective and Leakage for Dimple Assembly S01/20/A using the Monte Carlo Computer Code Monk,
   A.F. Course.

NEACRP-A- 641
   The Use of the MONK Monte Carlo Code for Whole Core Calculations for Fast Reactors,
   M.J. Grimstone.

NEACRP-A- 642
   Monte Carlo Calculations of the Dungeness 'B' Commissioning Experiments,
   I.J. Macbean, K. Robichaud.

NEACRP-A- 643
   A Small Reactor Neutronic Problem: Control Rod Efficiency of the Orphee Reactor calculated by the Monte Carlo Code Tripoli,
   L. Bourdet, C. Morin, J.C. Nimal.

NEACRP-A- 644
   Whole-Assembly calculations with Monte Carlo,
   R.D. McKnight, P.J. Collins.

NEACRP-A- 645
   A Monte Carlo Calculation for ZPPR-11B,
   P.J. Collins, R.D. McKnight.

NEACRP-A- 646
   Generalized Monte Carlo Perturbation Theory using Derivative Operators and Double Biasing Schemes,
   H. Rief.

NEACRP-A- 647
   Calculation of Multiplication Factors and Time-Decay Constants with the Monte Carlo Method,
   W. Matthes.

NEACRP-A- 648
   Modelling of Reactivity Interaction Effects in the Source Reactor Nestor,
   R.C. Bannerman.

NEACRP-A- 649
   GOLEM, A Versatile Scheme of Codes for Reactor Calculation,
   J. Porta, J.Y. Doriath

NEACRP-A- 650
   Status Report of the RERTR Program,
   A. Travelli.

NEACRP-A- 651
   Progress Report on Reactor Design,
   D.E. Bartine.

NEACRP-A- 652
   Analysis on the KUCA MEU Experiments (I),
   Seiji Shiroya, Masatoshi Hayashi, Keiji Kanda, Toshikazu Shibata.

NEACRP-A- 653
   Neutronics Design of Upgraded JRR-3 Research Reactor,
   H. Tsuruta, H. Ichikawa, J. Iwasaki.

NEACRP-A- 654
   USA Contribution Nuclear Data Base Assessment - Group H    Shielding (Chapter X, Section 2),
   Yousry Gohar, B.A. Engholm, R.W. Roussin, R.T. Santoro, A.B. Smith, C.C. Baker.

NEACRP-A- 655
   The Neutronics of INTOR/NET,
   C. Ponti.

NEACRP-A- 656
   Benchmark Experiments on a 60 cm-thick Li2O Slab Assembly and their Analysis,
   H. Kaekawa, Y. Ikeda, Y. Oyama, K. Tsuda, S. Yamaguchi, M. Nakagawa, T. Fukumoto, A. Hasegawa, T. More, Y. Seki, T. Nakamura.

NEACRP-A- 657
   Neutronic Experiments in a 120 cm. Lithium Sphere,
   K. Sugiyama, K. Kanda, S. Iwasaki, M. Nakazawa, H. Hashikura,
   T. Iguchi, H. Sekimoto, S. Itoh, K. Sumita, A. Takahashi, J. Yamamoto.

NEACRP-A- 658
   Measurements of Tritium Breeding Ratios in Lithium Slabs using Rotating Target Neutron Source,
   A. Takahashi, K. Yugami, K. Kohno, N. Ishigaki, J. Yamamoto and K. Sumita

NEACRP-A- 659
   Column Bowing and Inserted Reactivity in the HTGR Core,
   I. Otake.

NEACRP-A- 660
   Bowing Behaviour of Subassemblies in Experimental Fast Reactor "JOYO",
   Tetsuo Ikegami, Nobutatsu Mizoo, Yoshiaki Matsuno, Yoshio Watari.

NEACRP-A- 661
   The Effects of Subassembly Heterogeneity and Material Boundaries on the Sodium Voiding and Doppler Effects in a Sodium Cooled Fast Reactor,
   A.T.D. Butland.

NEACRP-A- 662
   Status of Argonne National Laboratory Methods Development to treat Heterogeneity Effects in Complex Geometries,
   R.N. Hwang.

NEACRP-A- 663
   Investigation of "low" and "high" heterogeneity effects at  the BFS-45 critical assembly,
   V.A. Dulin, A.V. Shapar.

NEACRP-A- 664
   Double Heterogeneity Effects on Criticality and Sodium Void Calculation of Fast Reactors,
   C. Gho, G. Palmiotti, M. Salvatores

NEACRP-A- 665
   Study of Neutron Absorption by Fission Products in a Critical Assembly,
   S.M. Bednyakov, V.A. Dulin, G.N. Manturov, V.K. Mozhaev.

NEACRP-A- 666
   The ARMA Experiment on Masurca, a Status Report,
   W. Scholtyssek, G. Granget.

NEACRP-A- 667
   Three-Dimensional Kinetics Analysis of Large LMFBR Cores with Thermal Hydraulic Feedback,
   Y. Oka, N. Tada, M. Konomura, S. Kondo and S. An.

NEACRP-A- 668
   Experimental Qualification of PWR Assemblies Calculation with Gadolinium Burnable Poisons,
   P. Chaucheprat, M. Darrouzet, L. Martin-Deidier, A. Santamarina.

NEACRP-A- 669
   Detailed Study on U232 and U236 in Uranium Recycling,
   Kazuki Hida, Sadao Kusuno and Ritsuo Yoshioka.

NEACRP-A- 670
   Critical Experiment with Thorium using Kuca,
   Keiji Kobayashi, Masatoshi Hayashi, Seiji Shiroya, JeijiKanda, Toshikazu Shibata, Naohiro Hirakawa, Kazutaka Ohashi, Shigeyasu Sakamoto, Otohiko Aizawa, Yuichi Ogawa, Kasuhiko Kudo.

NEACRP-A- 671
   Power Distribution and Control Rod Worth in Heavy-Water-Moderated, Cluster-type Plutonium Fuelled Core, Experiment and Analysis,
   Toshio Wakabayashi, Nobuo Fukumura, Yuuki Hachiya.

NEACRP-A- 672
   Critical Experiments on Poisoned Fuel Rods Containing 0.1-8.0 wt% GD2O3 in Light Water Lattices,
   Koichi Sakurada, Makoto Ueda, Yoshihira Ando, Tsutomu Yokoyama, Takeshi Seino.

NEACRP-A- 673
   Local Pin Power Prediction Applying Heterogeneous and Homogeneous Global Parameter Values,
   Flemming Nissen.

NEACRP-A- 674
   Measurements of Gamma-Ray Energy Deposition in a Heterogeneous Reactor Experimental Configuration and their Analysis,
   D. Calamand, R. de Wouters, A.D. Knipe, R. Menil.

NEACRP-A- 675
   Survey Analysis of Radiation Levels in the HTGR Regions,
   C.O. Slater, S.N. Cramer.

NEACRP-A- 676
   A U.S. Proposal for an International Intercomparison of Codes for Heat Transfer Assessment of Transportation Packages.

NEACRP-A- 677
   The Large Core Code Evaluation Working Group Benchmark Problem Four: Neutronics and Burnup Analysis of a Large Heterogeneous Fast Reactor, Part 1: Analysis of Benchmark Results,
   C.L. Cowan R. Protsik, J.W. Lewellen.

NEACRP-A- 678
   Some Remarks related to the C/E Trends for Power Distributions in Large Criticals,
   M. Salvatores.

NEACRP-A- 679
   Fission Distributions in a Critical Assembly with Two Internal Breeding Zones,
   S.P. Belov, A.I. Novozhilov.

NEACRP-A- 680
   Analysis of JOYO Burnup Data and their Interpretation in terms of Cross-Section Adjustment,
   Masatoshi kawashima, Tadashi Yoshida and Tetsuo Ikegami.

NEACRP-A- 681
   Radial Power Distribution Bias in the ZPPR-13A 700 MWe Radial Heterogeneous Reactor Critical Experiment,
   Mcfarlane et al.

NEACRP-A- 682
   Burnup Sensitivity Analysis in a Fast Breeder Reactor - Prediction
   Accuracy of Burnup Characteristics,
   Takanobu Kamei, Tadashi Yoshida, Toshikazu Takeda and Takuya Umano.

NEACRP-A- 683
   Burnup Sensitivity Calculation in a Fast Breeder Reactor with
   a Generalized Perturbation Theory,
   Toshikazu Takeda and Takuya Omano.

NEACRP-A- 684
   Actinide Integral Measurements on FCA for Evaluating and
   Improving Their Cross Section Data,
   T. Mukaiyama, M. Obu, M. Nakano, S. Okajima, T. Koakutsu.

NEACRP-A- 685
   Reduction of Uncertainties on the Components of the Reactivity
   Loss per Cycle - the Balzac Program on Masurca,
   A. d'Angelo, N. Karouby-Cohen, G. Palmiotti, G. Rimpault,
   M. Salvatores, R. Soule.

NEACRP-A- 686
   Analysis on Burnup Characteristics of Experimental Fast Reactor
   "JOYO" MK-I,
   Yoshio Watari, Kunikazu Kaneto, Shusaku Sawada, Kazuo Azekura,
   Hiroko Aizawa, Kotaro Inoue, Tetsuo Ikegami.

NEACRP-A- 687
   Comparison of Calculated and Experimental Reaction Rate
   Distributions and Associated Parameters in the Bizet Assemblies,
   J.M. Stevenson.

NEACRP-A- 688
   Pin-Plate Studies - A Comparison of ZPRR-12 and Cadenza Results,
   R.D. McKnight, P.J. Collins.

NEACRP-A- 689
   Reactivity Benchmark,
   L.G. Lesage

NEACRP-A- 690
   Benchmark on Recycling of Reprocessed Uranium,
   C. Golinelli, J.C. Guyot

NEACRP-A- 691
   Summary Conclusions of an NEACRP Sponsored Specialists' Meeting
   on Methods for Treating Unresolved Resonance Regions in Neutronics
   Calculations, held at OECD Headquarters, Paris, 26-27 January 1984.

NEACRP-A- 692
   Report on the 1984 ANS Reactor Physics and Shielding Topical,
   September 17-19, Chicago, IL.

NEACRP-A- 693
   Reactor Physics Calculations in connection with the Development
   of a 20% Enriched Fuel Element for DR3,
   C.F. Hojerup.

NEACRP-A- 694
   Summary Record of the 27th Meeting of NEACRP, Aix-en-Provence,
   22nd-26th October 1984. (Official minutes)
   Also NEANDC-A-200, SEN/NEACRP/M(85)1

NEACRP-A- 695
   Summary Record of the 27th Meeting of NEACRP, Aix-en-Provence,
   22nd-26th October 1984.
   Also NEANDC-A-197

NEACRP-A- 696
   Etude des methodes de calcul de l'autoprotection dans les resonances
   1ere partie.
   P. Ribon, V. Sauvinet, P. Moussalem
   Also CEA-N-2426

NEACRP-A- 697
   Summary Record of the 6th Meeting of the Scientific Co-ordination
   Group of the Joint Evaluated File Project, 14th-15th February 1985,
Paris
   Also JEF/DOC-90, NEANDC-A-199

NEACRP-A- 698
   Summary Record of a NEACRP Restricted Specialists' Meeting on the
   Intercomparison of methods for calculating shielded Cross Sections
   in the Unresolved Resonance Region, Santa Fe, 15th May 1985.

NEACRP-A- 699
   State of the Art on Reactor Noise Analysis
   P. Bernard, D. Fry, D. Stegemann, H. van Dam

NEACRP-A- 700
   NEA Data Bank Activity Report, November 1985.

NEACRP-A- 701
   A Glance at NEA's Programme of Work in the Nuclear Safety Area

NEACRP-A- 702
   CJD Activities in 1983-1985
   V.N. Manokhin et al.

NEACRP-A- 703
   Status Review of the High Priority Request List (September 1983 issue).

NEACRP-A- 704
   A Method for the Determination of Albedos for Nuclear Reactor Codes.
   O. Norinder

NEACRP-A- 705
   Three-Dimensional Multi-Group Neutron Transport Calculations by Double
Finite
   Element Method.
   T. Fujimura, Y. Nakahara and M. Obara

NEACRP-A- 706
   BERMUDA-3DN: A Three-Dimensional Neutron Transport Code in (x,y,z)
Geometry
   T. Susuki, A. Hasegawa and T. Ise.

NEACRP-A- 707
   Development of a Radiation Transport Code in the Three-Dimensional
(x,y,z)
   Geometry for Shielding Analysis
   T. Ida, Y. Oka, S. Kondo and Y. Togo.

NEACRP-A- 708
   Three-Dimensional Transport Calculation Method for Eigenvalue Problems
using
   Diffusion Synthetic Acceleration
   M. Bando, T. Yamomoto, Y. Saito, T. Takeda

NEACRP-A- 709
   Discrete Ordinates Transport Code in Hexagonal-Z Geometry.
   Y. Saito, M. Bando, T. Takeda

NEACRP-A- 710
   Three-Dimensional Transport Correction in Fast Reactor Core Analysis
   T. Takeda, Y. Sasaki, Y. Saito

NEACRP-A- 711
   Recent Developments of the Transport Theory Code MARC/PN
   J.K. Fletcher

NEACRP-A- 712
   BISTRO A Fast Two-dimension SN Transport Code for Keff Calculations
   C.J. Gho, G. Palmiotti, J.M. Rieunier, M. Salvatores

NEACRP-A- 713
   Spatial Kinetics Effects on Reactivity Measurements in ZPPR
   S.G. Carpenter, S.B. Brumbach, R.W. Goin

NEACRP-A- 714
   Some Methods of Taking in Account Spatial Effects at Reactivity Measurement
   Yu.A. Kazansky, V.A. Lititsky, I.P. Matveenko, A.G. Shokodko

NEACRP-A- 715
   252CR-Source-Driven Neutron Noise Analysis Method
   J.T. Mihalczo, W.T. King, E.D. Blakeman

NEACRP-A- 716
   Control Cluster Efficiency Measurements in PWRs by Analysing Power Signals during a Rod Drop
   J. Cray

NEACRP-A- 717
   Some Evidence of Space Kinetics Effects in Rod-Drop Experiments at Masurca
   J.P. West, J.C. Gauthier

NEACRP-A- 718
   Local Heterogeneity Effects on Small Sample Worths
   R.W. Schaefer

NEACRP-A- 719
   Experimental Study of Large Scale Axially Heterogeneous LMFBR Core at FCA Assembly XIII-1
   S. Iijima, S. Okajima, T. Sanda, M. Obu, T. Koakutsu, T. Hayase

NEACRP-A- 720
   A Method to Take in Account Control-Rod Heterogeneity Effects
   G. Palmiotti, D. Riou

NEACRP-A- 721
   Effective Beta Measurements on Uranium and Plutonium Fast Reactor Mockups
   E.F. Bennett and R.W. Schaefer

NEACRP-A- 722
   Beam Port Detector Response Calculations for the R2 Reactor
   R.M. Lell

NEACRP-A- 723
   The State of CADENZA and ZPPR-12 Analysis
   P.J. Collins

NEACRP-A- 724
   Prediction of K-Effective and Leakage for Dimple Assembly SO3/20/A using theMonte Carlo Computer Code MONK
   A.F. Course

NEACRP-A- 725
   Further Studies of the Prescott Interaction Problem using Superstage Powering in MONK 6.4
   R.J. Brissenden, N.R. Smith

NEACRP-A- 726
   A Review of Lattice Calculations for the PROTEUS-LWHCR Phase I Experiments
   R. Chawla

NEACRP-A- 727
   A Generalized Dancoff Factor for Application to HCPWR in Complex Lattice Arrangement
   Y. Ishiguro, K. Kaneko

NEACRP-A- 728
   The Study for the Control Rod Worth in High Conversion PWR
   E. Saji, A Takahashi, S. Uchida, K. Suzuki

NEACRP-A- 729
   Experimental Program and Results of Pre-analysis for a High Conversion Light Water Reactor (HCLWR) at FCA
   T. Osugi, H. Yoshida

NEACRP-A- 730
   Le Programme Experimental de Neutronique pour les Reacteurs a Eau Avances
   L. Martin-Deidier, S. Cathalau, A. Santamarina, M. Gomit

NEACRP-A- 731
   Tests of a Reactor Physics Calculational Model against Measured Results for Tight LWR Lattices
   E. Johansson

NEACRP-A- 732
   A Next Generation Steady State Neutron Source
   R.M. Moon, C.D. West

NEACRP-A- 733
   On the Neutronics of SINQ, a Continuous Spallation Neutron Source
   W.E. Fischer

NEACRP-A- 734
   IPNS Booster Target Neutronics Design Work
   R.N. Blomquist

NEACRP-A- 735
   Neutronics Study on Blanket System of High Tritium Breeding Ratio
   S. Mori, Y. Seki

NEACRP-A- 736
   A Cross-Section Sensitivity and Uncertainty Analysis on Fusion Reactor Blankets with SAD/SED Effect
   K. Furuta, Y. Oka, S. Kondo

NEACRP-A- 737
   Integral Experiments in a 120-CM Lithium Sphere
   K. Sugiyama, K. Kanda, S. Iwasaki, M. Nakazawa, H. Hashikura, H. Sekimoto, T. Iguchi, S. Itoh, K. Sumita, A. Takahashi, J. Yamamoto

NEACRP-A- 738
   Clean Benchmark Experiments and Analyses at FNS
   H. Maekawa

NEACRP-A- 739
   Activation Calculations for NET III A and FCTR
   C. Ponti

NEACRP-A- 740
   Some Remarks on the Feedback Coefficients at Phenix
   P. Coulon

NEACRP-A- 741
   Fusion Blanket Experiments
   T.J. Yule

NEACRP-A- 742
   Core Design and Performance of Small Inherently Safe LMRs
   Y. Orechwa, H. Khalil, E.K. Fujita, R.B. Turski

NEACRP-A- 743
   Fuel Management Studies of Small Metal and Oxide LMR's
   H. Khalil, E.K. Fujita, S. Yang, Y. Orechwa

NEACRP-A- 744
   Characteristics of Plutonium Utilization in ATR
   T. Wakabayashi, N. Tukumura, N. Aihara, S. Ohteru

NEACRP-A- 745
   Plutonium Recycling in the French PWRs

NEACRP-A- 746
   Burnup Characteristics of JOYO MK-II Core
   T, Ikegami, N. Mizoo

NEACRP-A- 747
   The Reactivity History of PFR during Period 1975 to 1984
   D.J. Lord

NEACRP-A- 748
   Uncertainties and Model Improvements for the Definition of a Lumped Fission Product for LMFBR Design Calculations
   N. Karouby-Cohen

NEACRP-A- 749
   Status of Reaction Rate Calibrations at ZPPR
   S.G. Carpenter

NEACRP-A- 750
   Intercomparison of Reaction Rate Measurement Techniques in MASURCA
   W. Scholtyssek, G. Granget

NEACRP-A- 751
   TMI-2 Criticality Studies: Lower-Vessel Rubble and Analytical Benchmarking
   R.M. Westfall, J.R. Knight, P.B. Fox, O.W. Hermann, J.C. Turner

NEACRP-A- 752
   NEACRP Statement on the Status Review of the High Priority Request List

NEACRP-A- 753
   Committee Summary Record of 28th Meeting of NEACRP, Madrid, 2nd - 6th November
   1985 (also NEANDC-A-208)

NEACRP-A- 754
   NEA Summary Record of 28th Meeting of NEACRP, Madrid, 2nd to 6th November
   1985 SEN/NEACRP/M(85)2 (Also NEANDC-A-221)

NEACRP-A- 755
   Committee Summary Record of 25th NEANDC Meeting, Paris/Grenoble, 18th - 22nd    November 1985
   (Also NEANDC-A-219)

NEACRP-A- 756
   NEA Summary Record of 25th Meeting NEANDC, Paris/Grenoble 18th-22nd November 1985 SEN/NEANDC/M(85)1
   (Also NEANDC-A-220)

NEACRP-A- 757
   IAEA MEETINGS

NEACRP-A- 758
   Summary Record of the 7th Meeting of the JEF Scientific Coordination Group.
   Also NEANDC-A-223

NEACRP-A- 759
   A proposed NEACRP/NEADB Reactor Physics Data Base and Validation System
   September 1986
   NEA Data Bank

NEACRP-A- 760
   NEA Data Bank Activity Report, September 1986

NEACRP-A- 761
   Summary report of the 19th Annual Meeting of IWGFR
   Kalpakkam, India, 11-14 March 1986

NEACRP-A- 762
   Report by the Secretariat on Recent Activities of the Committee on the Safety of Nuclear Installations of interest to NEACRP
   Also as SINDOC(86)148

NEACRP-A- 763
   IAEA Activities of potential interest to the NEACRP

NEACRP-A- 764
   Evaluation of Delayed Neutron Data for Thermal Fission of U-235 Based on Integral Experiments using SHE
   Y. Kaneko, F. Akino, T. Yamane

NEACRP-A- 765
   Status of Evaluated Precursor and Aggregate Spectrum
   T.England, et al.

NEACRP-A- 766
   Some Investigations on the Reactivity Scale for the Super-Phenix Start Up Experiment Analysis
   A. D'Angelo, B. Vuillemin, J.C. Cabrillat

NEACRP-A- 767
   Comparison of WIMS Predictons with Reactivity Measurements made on Samples of Irradiated DRAGON Fuel in the HECTOR reactor
   J. Marshall, J.L. Hutton

NEACRP-A- 768
   Fission-Product Yield Data for the US/UK Joint Experiment in the Dounreay Prototype Fast Reactor
   J.K. Dickens, S. Raman

NEACRP-A- 769
   Integral-Data Test of JEF-1 Fission-Product Cross Sections
   A.J. Jansson, et al.

NEACRP-A- 770
   An Investigation of Neutron Absorption by Fission Products using the Reactivity Perturbation Method
   S.M. Bednyakov

NEACRP-A- 771
   System Dynamics Analysis for Mitigating ATWS Consequences of a 1000 MWe  Loop-Type LMFBR
   K. Yamaguchi, H. Endo

NEACRP-A- 772
   LMR Core Design for Inherent Safety
   D.C. Wade

NEACRP-A- 773
   Implications of the EBR-II Inherent Safety Demonstration Test
   H.P. Planchon, et al.

NEACRP-A- 774
   The ZPPR-15A IFR Critical Experiments Program: Early Results from a Pu/U Metal Fuel Core Simulation

NEACRP-A- 775
   Improved Locations of Reactivity Devices in Future CANDU Reactors Fuelled with Natural Uranium or Enriched Fuels
   P.G. Boczar, M.T. van Dyk

NEACRP-A- 776
   A Coarse Mesh 3-D Transport Calculation Code with Diffusion Synthetic Acceleration
   H. Sakuma, N. Ito, T. Takeda

NEACRP-A- 777
   Review of Application and Improvement of a Three-Dimensional Discrete Ordinates Transport Code ENSEMBLE
   T. Nishimura, et al.

NEACRP-A- 778
   Three-Dimensional Oak Ridge Transport Code (TORT)

NEACRP-A- 779
   RITME: A Fast Computing Simulator for 3-D Power Distribution Calculations in Large PWR Cores
   P. Bernard, et al.,

NEACRP-A- 780
   EAC: The Modular European Accident Code for LMFBR Safety Analysis
   G. Van Goethem, et al.

NEACRP-A- 781
   Method of Characteristics in the Regions with Complex Geometry
   J.R. Suslov

NEACRP-A- 782
   Spatial Kinetics Effects in Reactivity Measurements in ZPPR
   S.G. Carpenter, S.B. Brumbach, R.W. Goin

NEACRP-A- 783
   Taking Account of Spatial Effects in Reactivity Measurement by the Inverse Kinetics Method
   V.A. Lititsky, I.P. Matveenko, A.G. Shokodko

NEACRP-A- 784
   The Enhancement of Control Rod Worths in Fast Rectors by the Introduction of Moderators
   G. Ingram, M.J. Grimstone

NEACRP-A- 785
   Experimental Study of Large Scale Axially Heterogeneous LMFBR Core at FCA Assembly XIII
   S. Iijima, et al.

NEACRP-A- 786
   Two Dimensional Cell Heterogeneity Effect in Analysis of Fast Critical Assemblies
   T. Takeda, et al.

NEACRP-A- 787
   Parametric Experiments on Control Rod Heterogeneity in the Framework of the BALZAC Program
   Y.C. Kim, et al.

NEACRP-A- 788
   Measurements and Calculations of B-10 (n,He) and U-235 (n,f) Reaction Rates in a Control Rod Mock-up in ZPPR
   S.B. Brumbach, et al.

NEACRP-A- 789
   Breeding Characteristics of Fast Sodium Reactors with Heterogeneous Core
   P.N. Alekseev

NEACRP-A- 790
   Summary of Recent Results from the JAERI/US Fusion Neutronics Phase I Experiments
   T. Nakamura, M.K. Abdou

NEACRP-A- 791
   Measured Neutron Parameters for Phase I Experiments at the FNS Facility
   H. Maekawa, et al.

NEACRP-A- 792
   Neutronics Experiments in a Li-Pb Spherical Assembly
   K. Sugiyama, et al.

NEACRP-A- 793
   First Results of LBM Experiment at Lotus and its Analysis
   P.A. Haldy, J. Stepanek

NEACRP-A- 794
   Neutron Flux Measurements for the Lithium-Tritium Sweep Gas Tests
   E.F. Bennett, T.J. Yule

NEACRP-A- 795
   Neutron Flux Measurements for the Lithium-Tritium Sweep Gas Tests
   R.E. Donders, et al.

NEACRP-A- 796
   Analysis of Nuclear Characteristics of Chernobyl Reactor by WIMS-ATR Code
   T. Wakabayashi, N. Fukumura

NEACRP-A- 797
   Initial Critical Experiments in FCA-HCLW Core
   T. Osugi, et al.

NEACRP-A- 798
   Proposal of Benchmarks on Data and Method to Calculate Reactor Characteristics in High Conversion Light Water Reactors
   Y. Ishiguro, H. Akie, H. Takano

NEACRP-A- 799
   Sensitivity Analysis of Cell Parameters in High-Conversion Light Water Reactors
   M. Nakano, T. Takeda, H. Takano

NEACRP-A- 800
   Computational Breakdown of the HCLWR Infinite Lattice Void Reactivity into Contributing Nuclides and Energy Groups
   K. Nishina, K. Okumura

NEACRP-A- 801
   Validation of HELIOS.HX Code for HCLWR Lattice Analysis
   Y. Yamamoto, et al.

NEACRP-A- 802
   The Effect of Fission Products on Burn-Up Characteristics in High Conversion Light Water Reactors
   H. Takano, H. Akie, Y. Ishiguro

NEACRP-A- 803
   Special ZPPR Experiments on Sodium Manometer Worth and Core Axial Expansion Worth

NEACRP-A- 804
   Development of the Traditional Group Diffusion Method on to a Correct Representation of Bilinear Functionals
   M.F. Vorotynstev, A.A. Rineysky

NEACRP-A- 805
   A Data Base System for Reactor Physics Experiments at the Critical Assembly of Kyoto University
   C. Ichihara

NEACRP-A- 806
   A Computer Code System for Integral Experiment Data Bank
   Y. Naito

NEACRP-A- 807
   Critical (Integral) Experiment Data Banking: ZPPR Perspective
   L.G. LeSage

NEACRP-A- 808
   Verification of BNAB-78 Constants Set by the Basis of Integral Experiment Data  Bank
   A.M. Taybulya, et al.

NEACRP-A- 809
   BDI: The Cadarache Data Bank for LMFBR Integral Experiment Data
   G. Rimpault, G. Reynaud

NEACRP-A- 810
   Status Report: OECD-NEACRP Working Group on Criticality Calculations
   G.E. Whitesides

NEACRP-A- 811
   Intercomparison of Cross-Section Libraries used for Spent Fuel Caskm Shielding Analyses
   C.V. Parks, et al.

NEACRP-A- 812
   SHETAN Calculation of a Cruciform Absorber Benchmark
   F.C. Wong, J.D. Irish

NEACRP-A- 813
   SEN/NEACRP/M(86)2 (also NEANDC- A) Summary Record of 29th Meeting of  NEACRP Committee, Chalk River

NEACRP-A- 814
   Also NEANDC- A : Summary Record (Blue cover) of 29th Meeting of NEACRP in Chalk River, Canada
   Compiled by J.M. Stephenson

NEACRP-A- 815
   Call for papers - Specialist Meeting on Data for Decay Heat Predictions

NEACRP-A- 816
   Survey on manpower available in the field of Nuclear Data for Applications In OECD countries. 1985
   K. Boeckhoff and C. Buerkholz
   816bis sent by author on 19.9.88

NEACRP-A- 817
   Summary Record of the 8th JEF scientific coordination group

NEACRP-A- 818
   List of CSNI International Standard Problems
   Nuclear Energy Agency
   August 1987

NEACRP-A- 819
   Reproduction and Distribution of the Documents of the NEACRP
   NEACRP Secretariat
   1987

NEACRP-A- 820
   Steering Committee for Nuclear Energy: Renewal of the Mandate of the NEACRP Terms of Reference
   Nuclear Energy Agency
   1987

NEACRP-A- 821
   NEA Data Bank Activity Report 1986 - 1987
   NEA Data Bank
   September 1987

NEACRP-A- 822
   Report by the Secretariat on Recent Activities of the CSNI of Interest to the Committee on Reactor Physics
   Nuclear Energy Agency CSNI Secretariat
   September 1987

NEACRP-A- 823
   Summary of the NEACRP Specialist Meeting on Shielding Benchmarks
   OECD, Paris, 13-14th October 1986
   NEACRP Secretariat
   Paris 13-14 October 1986

NEACRP-A- 824
   Report on Relevant IAEA Activities to the NEACRP.
   IAEA
   September 1987

NEACRP-A- 825
   Analysis of the Chernobyl Reactor Accident (I). Nuclear and Thermal  Hydraulic Characteristics and Follow-up Calculation of Accident. PNC.
   T. Wakabayashi et Al.
   September 1987

NEACRP-A- 826
   Analysis of the Chernobyl Reactor Accident (II). An Examination of the Improvement Measures concerning the Accident of Chernobyl Power Plant.
   PNC.
   T. Wakabayashi et Al.
   September 1987

NEACRP-A- 827
   An Analysis of Reactivity Coefficients of the Chernobyl Reactor by Cell Calculation. JAERI.
   K. Tsuchihashi, F. Akino
   September 1987

NEACRP-A- 828
   Measurements of Void Reactivity Effects in CIRENE Mock-up Fuel Channels At RB-3. ENEA.
   A. Grossi, A. Vanossi
   September 1987

NEACRP-A- 829
   A Guide to the Use of "KENO-EUR" A Code for Perturbation Analysis in Multiplying Systems. JRC.
   H. Rief
   July 1987

NEACRP-A- 830
   An Assessment of Lattice Characteristics that Influence Coolant Void Reactivity in CANDU-type Lattices. AECL.
   J. Griffiths, P.G. Boczar, M.T. van Dyk
   August 1987

NEACRP-A- 831
   The Chernobyl Accident. Multidimensional Simulations to Identify the Role of Design and Operational Features of the RBMK-1000. AECL.
   P.S.W. Chan et Al.
   August 1987

NEACRP-A- 832
   Review of Prototype Fast Reactor (PFR) Reactivity Feedback Coefficient Measurements 1974-1978. UKAEA.
   D.J. Lord et Al.
   June 1987

NEACRP-A- 833
   Uncertainty Analysis on the Measurement and Calculation of Feedback Effects in LMFBR. Application of SUPER-PHENIX-1 Start-Up Experiments
   CEA.
   P. Bergeonneau, M. Salvatores, M. Vanier
   August 1987

NEACRP-A- 834
   A Simplified Analysis of Uncertainty Propagation in Inherently Controlled ATWS Events. ANL.
   D.C. Wade
   September 1987

NEACRP-A- 835
   Uncertainties in Coefficients of Reactivity of the BN-Type Fast Reactors. Obninsk.
   I.A. Kuznetsov, I.P. Matveenko
   September 1987

NEACRP-A- 836
   On the Reactivity Effects of Nuclear Fuel Fragmentation with Reference to  the Chernobyl Accident. VTT.
   F. Wasastjerna
   September 1987

NEACRP-A- 837
   Integral Experiment Analysis on Refinement of Rhodium-103 and Palladium-105 Capture Cross-Sections in Fast Critical Assemblies. USSR.
   S.M. Bednyakov
   September 1987

NEACRP-A- 838
   Analysis of Experiments on Critical Assemblies for Testing the Constant Support of Reactor Calculations. USSR.
   E.A. Gomin et Al.
   September 1987

NEACRP-A- 839
   The Concept of Fast Sodium Power Reactor with In-Assembly Heterogeneity.
   Kurchatov Institute.
   V.V. Orlov et Al.
   September 1987

NEACRP-A- 840
   Comparison Between Calculated and Experimental Effective Beta Results on ZPPR and SNEAK Fast Facilities. ENEA/CEA.
   A. D'Angelo, M. Salvatores
   August 1987

NEACRP-A- 841
   Calculation of Integrated Characteristics of Delayed Neutrons. USSR.
   L.G. Manevich et Al.
   September 1987

NEACRP-A- 842
   Neutronic Experimental Program in France for the Qualification of Unmoderated PWR Calculation. CEA
   M. Darrouzet et Al.
   September 1987

NEACRP-A- 843
   Results and Analyses for FCA Phase-1 Experiment on High Conversion Light Water Reactor. JAERI.
   T. Osugi et Al.
   September 1987

NEACRP-A- 844
   Some Special Methodical and Nuclear Data Investigations for Tight Lattice PWR-Cores (HCLWR and PROTEUS). KFK.
   C.H.M. Broeders, A. Mateeva, H. Kuesters
   September 1987

NEACRP-A- 845
   Uncertainty Evaluation of Void Reactivity Worth in High Conversion Light Water Reactors. Osaka University.
   Y. Yamaguchi, T. Takeda
   September 1987

NEACRP-A- 846
   Investigation of the Void Coefficient and Other Integral Parameters in the PROTEUS-LWHCR Phase II Programme. EIR/KWU/KFK.
   R. Seiler et Al.
   September 1987

NEACRP-A- 847
   Amelioration de la Connaissance de la Capture des Produits de Fission dans les Reacteurs a Eau. CEA.
   L. Martin-Deidier, J. Krebs
   September 1987

NEACRP-A- 848
   Recent Data and Method Improvements for the Pseudo-Fission Product Cross-Sections Assessment in a LMFBR. CEA.
   L. Martin-Deidier, M. Salvatores
   August 1987

NEACRP-A- 849
   Preliminary Report of HCLWR Cell Burn-up Benchmark Calculations. JAERI.
   H. Akie, Y. Ishiguro, H. Takano
   September 1987

NEACRP-A- 850
   CEA Contribution to the HCLWR Burn-up Benchmark Proposed by NEACRP. CEA.
   P. Chaucheprat
   September 1987 (Revision December 1987)

NEACRP-A- 851
   EIR Results for the HCLWR NEACRP Burn-up Benchmark Obtained using EIR Version of DANDE System and JEF Library. EIR.
   J. Stepanek and P. Vontobel
   September 1987

NEACRP-A- 852
   Inherent Safety Performance of a Mixed-Oxide-Fueled 1000 MWe Loop-Type LMFBR under ATWS Conditions. PNC/NAIG/Toshiba.
   K. Yamaguchi, S. Ohta, H. Endo
   September 1987

NEACRP-A- 853
   Trends vs Reactor Size of Passive Reactivity Shutdown and Control Performance. ANL.
   D.C. Wade, E.K. Fujita
   September 1987

NEACRP-A- 854
   A Simplified Model of Core Thermal Dilation. ANL.
   T.J. Moran
   September 1987

NEACRP-A- 855
   A Technique for Computing Bowing Reactivity Feedback in LMFBR's. ANL.
   P.J. Finck
   September 1987

NEACRP-A- 856
   Optimisation of Reactivity Effects in Fast Reactors. Kurchatov Institute.
   P.N. Alekseev, I.S. Slesarev, M.V. Trunov
   September 1987

NEACRP-A- 857
   Fusion Blanket Engineering Benchmark Experiments - JAERI/USDOE Collaborative Program Phase II. JAERI/USDOE.
   T. Makamura
   September 1987

NEACRP-A- 858
   Error and Uncertainty Analysis of Neutron Transport Calculation. University of Tokyo.
   K. Furuta, Y. Oka, S. Kondo
   September 1987

NEACRP-A- 859
   On the Proposal of International Comparison of the Measuring Techniques for Tritium Production Rate Used for Fusion Neutronics Experiment. FRPL.
   Y. Kaneko, T. Nakamura, H. Maekawa
   September 1987

NEACRP-A- 860
   Neutron Spectrum Measurements with Proton Recoil Counters at FNS. ANL.
   E.F. Bennett
   September 1987

NEACRP-A- 861
   Simulation of Detailed Space - Energy Distribution of Neutrons in Intermediate Reactors. Kurchatov Institute.
   A.G. Morozov, I.S. Slesarev
   September 1987

NEACRP-A- 862
   EURACOS Iron and Sodium Benchmark Analysis. A Comparison of JEF-1 and BMCCS In Cross-Sections in Cross-Sections in Deep Penetration Experiments. JRC.
   September 1987

NEACRP-A- 863
   Draft Report on Criticality Benchmarks (and Memo). ORNL
   G.E. Whitesides
   September 1987

NEACRP-A- 864
   Summary of the Second Meeting on the NEACRP Intercomparison of Codes for the Shielding Assessment of Transportation Packages. AEE Winfrith.
   A. Avery
   September 1987

NEACRP-A- 865
   Status of IRMA. ANL.
   S.G. Carpenter
   September 1987

NEACRP-A- 866
   Thermal Fission Product Benchmarks. AEE Winfrith.
   M.J. Halsall
   September 1987

NEACRP-A- 867
   C.E.A. Contribution to the Thermal Fission Product Benchmark Proposed by NEACRP. CEA.
   P. Chaucheprat
   September 1987

NEACRP-A- 868
   The Third Meeting on the Status of Reactor Physics in the Nordic Countries.
   VTT.
   September 1987

NEACRP-A- 869
   Application of Critical Experiments and Operating Data to Core Design in Formal Measurements of Cross-Section Data Adjustment. ANL.
   Proposal Specialists Meeting
   September 1987

NEACRP-A- 870
   Future Management of the WIMS Group of Codes at Winfrith. AEE Winfrith.
   September 1987

NEACRP-A- 871
   Summary Record of the 30th NEACRP Meeting held at Helsinki from 14th to 18th September 1987.
    NEANDC-A-244
   J.M. Stevenson
   September 1987

NEACRP-A- 873
   Summary Record of the 26th NEANDC Meeting held at Rome from 18th to 22th May 1987. SEN/NEANDC/M(87)1
   May 1987

NEACRP-A- 874
   Summary on SMORN-V
   Munich, October 12-18, 1987.
   W. Bastl
   30 October 1987

NEACRP-A- 875
   Specialists' Meeting on the NEACRP Burnup Benchmark Calculations for High Conversion Light Water Reactor Lattices. Paris, 18-22 April 1988.
   First Circular
   Y. Ishiguro , E. Sartori
   17 December 1987

NEACRP-A- 876
   Specialists' Meeting on the Application of Critical Experiments and Operating Data to Core Design via Formal Methods of Cross Section Data Adjustment. Jackson Hole, 23-24 September 1988.
   First Circular
   D. C. Wade
   5 April 1988

NEACRP-A- 877
   NEACRP Criticality Working Group Meeting, 28-30 June 1988
   First Circular
   NEACRP Secretariat
   16 May 1988

NEACRP-A- 878
   Summary Record of the Ninth Meeting of the Scientific Coordination Group of the Joint Evaluated File Project.
   JEF Secretariat
   Paris 14 April 1988

NEACRP-A- 879
   International Comparison of Tritium Production Rate Measurements for Fusion Neutronics Research.
   Y. Kaneko, T. Nakamura
   June 1988

NEACRP-A- 880
   A Glance at NEA's Programme of Work in the Nuclear Safety Area.
   CSNI Secretariat
   June 1988

NEACRP-A- 881
   Proposal of 3-D Neutron Transport Benchmark Problems
   T. Takeda M. Tamitani and H. Unesaki
   Draft, September 1988

NEACRP-A- 882
   Reduction of Void Reactivity in Light Water Cooled, Heavy Water Reactors
   R. Martinelli, A.R. Dastur, H.C. Chow
   ENEA Roma
   Session 2.6 - 31st NEACRP Meeting O-arai

NEACRP-A- 883
   Summary of "Specialists' Meeting on In-core Instrumentation and Reactor Core Assessment", Cadarache, France, June 1988
   R. Martinelli, ENEA
   Chairman Summary unavailable at the time of 31st NEACRP Meeting

NEACRP-A- 884
   Shielding Experimental Benchmark Data Base at the Nuclear Energy Agency Data Bank.
   7th International Conference on Radiation Shielding, Bournemouth,
   12-16 September 1988
   P. Miller, P. Nagel, M. Salvatores, E. Sartori

NEACRP-A- 885
   Progress Report from NEA Data Bank, October 1988
   NEACRP Secretariat
   31st NEACRP; Session A 5

NEACRP-A- 886
   Overview of the IAEA Reactor Physics Activities, September 1988
   M. Crijns
   31st NEACRP : Session A 5.

NEACRP-A- 887
   Fast Breeder Reactor Advanced Core Studies in France
   October 1988
   J. Ravier, J. Berthet, H. Sztark
   Session B 1.1 - 31st NEACRP Meeting

NEACRP-A- 888
   A Limited Survey of the Gamma-Heating Measurements and their Role in Validating the French LMFBR Calculational Methods and Data During the Period 1982-1990
   D. Calamand, CEA Cadarache
   Session B 1.3 - 31st NEACRP Meeting

NEACRP-A- 889
   Prompt Gammas Emitted in Fission
   October 1988
   E. Fort, J. Frehaut, P. Long
   Session B 1.3 - 31st NEACRP Meeting

NEACRP-A- 890
   Analysis of a Control-Rod Ejection Transient in a Mox-Fuelled PWR
   October 1988
   M. Lam Hime, R. Lenain, G. Mathonniere, J.P. Perrutel, M. Rohart, H. Schaeffer, S. Stelletta
   Session B 1.4 - 31st NEACRP Meeting

NEACRP-A- 891
   MORGANE/S : Fission Product Capture Measurements in a HCLWR Tight Lattice
   October 1988
   J. Mondot, J.M. Gomit, C. Garzenne, P. Chaucheprat, A. Santamarina
   Session B 2.3 - 31st NEACRP Meeting

NEACRP-A- 892
   SUPER-PHENIX Effective Beta : Calculated Values Comparison
   October 1988
   A. D'Angelo
   Session 2.4 - 31st NEACRP Meeting

NEACRP-A- 893
   Investigations of an Advanced Reactor With Pu Fuel Controlled without Soluble Boron
   October 1988
   J. Bergeron, R. Lenain
   Session B 2.5 - 31st NEACRP Meeting

NEACRP-A- 894
   IRMA : Interlaboratory Comparison of Fission and Capture Rate Measurement Techniques at MASURCA
   W. Scholtyssek, M. Angelone, P. D'Hondt, G. Granget, B.L.H. Burbridge, K. Gmuer, D. Maddison, P. Marimbeau
   Session B 4.5 - 31st NEACRP Meeting - also NEACRP-L-315

NEACRP-A- 895
   Progress with the NEACRP Intercomparison of Codes for the Shielding Assessment of Transportation Packages. October 1988
   A. Avery
   Session B 4.3 : 31st NEACRP Meeting

NEACRP-A- 896
   Preliminary Study on the Feasibility of Ductless Fuel Assembly for Fast Reactors. October 1988
   I. Shibahara and Y. Enokido
   Session B 1.1 : 31st NEACRP Meeting

NEACRP-A- 897
   A High Breeding Fast Reactor With a New Concept of Metallic Fuel Assemblies.
   Int. Reactor Physics Conf. 88, Jackson Hole
   T. Hiraoka, K. Sako, H. Takano, M. Osakabe
   Session B 1.1 : 31st NEACRP Meeting

NEACRP-A- 898
   Analysis of the Partial-Refueling Type Ultra Long Life Core Using Metallic Fuels for 1000 MWe-LMFBRs. October 1988
   K. Kawashima and R.A. Karam
   Session B 1.1 : 31st NEACRP Meeting

NEACRP-A- 899
   Assessment of LMFBR Core Design Concepts Using Metallic Fuels
   Int. Reactor Physics Conf. 88, Jackson Hole
   T. Nishimura, Y. Yokoo, Y. Tanaka, K. Kawashima, I. Kakehi, M. Kawashima,, T. Hojuyama
   Session B 1.1 : 31st NEACRP Meeting

NEACRP-A- 900
   Transmutation of Transuranic Wastes by Proton-induced Nuclear Spallation Reactions, October 1988
   T. Nishida, Y. Nakahara, I. Kanno, H. Takada, Y. Kaneko
   Session B 1.2 : 31st NEACRP Meeting

NEACRP-A- 901
   Conceptual Study of Actinide Burner Reactors
   Int. Reactor Physics Conf. 88, Jackson Hole
   T. Mukaiyama, H. Takano, T. Takizuka, T. Ogawa, M. Osakabe
   Session B 1.2 : 31st NEACRP Meeting

NEACRP-A- 902
   Analysis of ZPPR-17A Gamma Heating Experiments
   October 1988
   H. Unesaki and P.J. Collins
   Session B 1.3 : 31st NEACRP Meeting

NEACRP-A- 903
   On the Passive Safety of OTTO and Multipass Fuel Cycles of Modular High Temperature Reactor and Concept of Fuel Discharge Safe Reactor.
   October 1988
   H. Sekimoto, P.H. Liem, Y.H. Rose, E. Suetomi
   Session B 2.1 : 31st NEACRP Meeting

NEACRP-A- 904
   Measurement of Feedback Reactivity of Experimental Fast Reactor JOYO.
   October 1988
   T. Aoyama, Y. Arii, N. Mizoo
   Session B 2.1 : 31st NEACRP Meeting

NEACRP-A- 905
   The Concept of High Conversion Light Water Reactor with Flat Core and its Applications.
   Int. Reactor Physics Conf. 88, Jackson Hole
   Y. Ishiguro, K. Okumura, H. Akie, T. Mori, H. Takano
   Session B 2.5 : 31st NEACRP Meeting

NEACRP-A- 906
   Reactor Physics Experiments on High Conversion Light Water Reactor at Plutonium Fueled FCA-XV 1 Core.
   Int. Reactor Physics Conf. 88, Jackson Hole
   T. Osugi, S. Okajima, M. Obu, T. Sakurai
   Session B 2.5 : 31st NEACRP Meeting

NEACRP-A- 907
   The Sensitivity of Coolant Void Reactivity at High Voidage for Tight Pitch Lattice. October 1988
   Y. Yamaguchi and T. Takeda
   Session B 2.5 : 31st NEACRP Meeting

NEACRP-A- 908
   Study on Coolant Void Reactivity of Pressure Tube Type Heavy Water Lattice by Substitution Method.
   Nucl. Sci. and Eng. 1988
   Y. Kowata and N. Fukumura
   Session B 2.6 : 31st NEACRP Meeting

NEACRP-A- 909
   Proposal of International Comparison on Measuring Techniques of Tritium Production Rate for Fusion Neutronics Experiment.
   October 1988 (Revision of NEACRP-A-859)
   T. Nakamura, H. Maekawa and P. Haldi
   Session B 4.8 : 31st NEACRP Meeting

NEACRP-A- 910
   Actinide Transmutation by Spallation in the Light of Recent Cyclotron Development
   P. Bonnaure, H. Rief, P. Mandrillon, H. Takahashi
   Session B 1.2 : 31st NEACRP Meeting

NEACRP-A- 911
   Nuclear Transmutation of Radioactive Waste: A Review of the State of the Art
   E. Schmidt
   Session B 1.2 : 31st NEACRP Meeting

NEACRP-A- 912
   Review of Actinide Monitoring at the JRC - Ispra
   W. Hage
   Session B 1.5 : 31st NEACRP Meeting

NEACRP-A- 913
   Some Applications of Stochastic Processes in Neutron Coincidence Measurements used in Nuclear Safeguards
   W. Matthes
   Session B 1.5 : 31st NEACRP Meeting

NEACRP-A- 914
   Feasibility Studies of Passive Safeguards Interrogation of Irradiated Fuel Containers.
   Y. Yeivin, H. Rief, G. Gonano, R. Van Heusden
   Session B 1.5 : 31st NEACRP Meeting

NEACRP-A- 915
   Construction of a Neutron Deep Penetration Sodium Shield Mock-up
   G. Perlini, S. Acerbis, U. Canali, G. Gonano, R. Nicks, H. Rief
   Session B 4.1 : 31st NEACRP Meeting

NEACRP-A- 916
   Neutronic Spectrometry Measurements in Sodium
   G. Perlini, S. Acerbis
   Session B 4.1 : 31st NEACRP Meeting

NEACRP-A- 917
   Neutron Spectrometry Measurements in Iron
   G. Perlini, M. Carter, S. Acerbis
   Session B 4.1 : 31st NEACRP Meeting

NEACRP-A- 918
   Fission Neutron Penetration in Iron and Sodium.
   Part I: Activation Measurements
   R. Nicks, G. Perlini, H. Rief
   Session B 4.1 : 31st NEACRP Meeting

NEACRP-A- 919
   Fission Neutron Penetration in Iron and Sodium.
   Part II: Neutron Spectrometry
   R. Nicks, G. Perlini, H. Rief
   Session B 4.1 : 31st NEACRP Meeting

NEACRP-A- 920
   Interpretation of EURACOS Iron and Sodium Benchmarks
   G. Perlini, H. Rief, E. Vittone, K. Burn
   Session B 4.1 : 31st NEACRP Meeting

NEACRP-A- 921
   Thermal Fission Product Benchmark.
   October 1988
   M.J. Halsall, C.J. Taubman
   Session B 4.6 : 31st NEACRP Meeting

NEACRP-A- 922
   Experiments and Analysis for an Axially Heterogeneous LMR Assembly at ZPPR.
   P.J. Collins, S.B. Brumbach
   Session B 1.1 : 31st NEACRP Meeting

NEACRP-A- 923
   Physics Studies of Higher Actinide Consumption in an LMR.
   R.N. Hill
   Session B 1.2 : 31st NEACRP Meeting

NEACRP-A- 924
   Analysis of Gamma Ray Heating Measurements in ZPPR-17A.
   P.J. Collins and H. Unesaki
   Session B 1.3 : 31st NEACRP Meeting

NEACRP-A- 925
   Limitations of Nondestructive Analysis.
   P.J. Persiani
   Session B 1.5 : 31st NEACRP Meeting

NEACRP-A- 926
   Status of Radiation Damage Studies in the US LMR Program.
   Y. Orechwa
   Session B 1.7 : 31st NEACRP Meeting

NEACRP-A- 927
   Radial Expansion Feedback in LMR's: an Assessment of Neutronic Approximations.
   Int. Reactor Physics Conf. 88, Jackson Hole
   P.J. Finck and T.J. Moran
   Session B 2.1 : 31st NEACRP Meeting

NEACRP-A- 928
   Radial Core Expansion Reactivity Feedback in Advanced LMR's:  Uncertainties and their Effects on Inherent Safety
   ANS Topical Meeting, Seattle, April 1988
   R.A. Wigeland and T.J. Moran
   Session B 2.1 : 31st NEACRP Meeting

NEACRP-A- 929
   Proposed 3D Neutron Transport Benchmark Computations
   (Input to the proposed 3D Transport Benchmark)
   E.M. Gelbard, R.W. Schaefer
   Session B 4.9 : 31st NEACRP Meeting

NEACRP-A- 930
   Some Technical Comments on the Proposed International Comparison of TPR Measurement Schemes
   K.G. Porges
   Session B 4.8 : 31st NEACRP Meeting

NEACRP-A- 931
   Calculation of EURACOS Iron Benchmark Experiment Using the Hybrid Method.
   Yen-Yan H. Liu, Chin Chun Wun, H. Rief
   Session B 4.1 - 31st NEACRP Meeting

NEACRP-A- 932
   Report of the NEANDC Subcommittee on Evaluation Cooperation
   26 September 1988
   C. Dunford, E. Fort, S. Igarasi, C. Nordborg, F. Perey, J. Rowlands, M. Salvatores, A. Smith, M. Sowerby, P. Young
   Session A 8 - 31st NEACRP Meeting

NEACRP-A- 933
   Quality Assurance Activities at the Data Bank
   10-11 October 1988
   L. Garcia de Viedma, L.H. Underhill
   Action 7 - 31st NEACRP Meeting

NEACRP-A- 934
   Brief Summary of 7th International Conference on Radiation Shielding
   Bournemouth, 12-16 September 1988
   E. Sartori
   Session B 5.1 - 31st NEACRP Meeting

NEACRP-A- 935
   Progress Report on the JEF Project
   September 1987 - October 1988
   M. Salvatores

NEACRP-A- 936
   OECD-NEA Working Group on Criticality Calculations
   Meeting, Paris 27-30 June 1988
   G. E. Whitesides

NEACRP-A- 937
   The Experimental and Calculated Investigations of Fast Reactor Models with Axial Heterogeneity.
   October 1988
   S.P. Belov, A.L. Kochetkov, V.I. Matveev, I.P. Matveenko, A.V. Shapar

NEACRP-A- 938
   On Realization of the Self-Protectiveness Principle in Reactors with Fast Resonance Neutron Spectrum
   October 1988
   I.S. Slesarev, V.V. Kuznetsov, A.G. Morozov, P.N. Alekseev, V.A, Stukalov, Yu.A. Zverkov

NEACRP-A- 939
   The Study of Problems of the Physics of Reactors with Fast Resonance Neutron Spectrum
   October 1988
   A.G. Morozov, I.S. Slesarev

NEACRP-A- 940
   The Current State of Investigations Dealing with the Main Stable Fission Products Capture Cross-Sections at the BFS Critical Assemblies
   October 1988
   S.M. Bednyakov, G.N. Manturov

NEACRP-A- 941
   Reduction of Long-Term Potential Hazard of Spent Fuel from CANDU Reactors by Heavy Element Recycles
   R.B. Lyon

NEACRP-A- 942
   The Sensitivity of MAPLE-X10 Core Reactivity and the Control Absorber Worth to Variations in the 3D Coolant Void Distribution
   H.J. Smith

NEACRP-A- 943
   District Heating with Slowpoke Energy Systems
   G.F. Lynch

NEACRP-A- 944
   The Nuclear Battery: A Solid State, Passively Cooled Reactor for the Generation of Electricity
   K.S. Kozier, H.E. Rosinger

NEACRP-A- 945
   Neutronics Design of a Small, Solid State ,Passively Cooled Reactor,  The Nuclear Battery
   J.V. Donnelly, K.S. Kozier, G.R. Penner

NEACRP-A- 946
   Startup of the Slowpoke Demonstration Reactor and Low Power Tests
   J.D. Irish, B.M. Townes, C.M. Tseng

NEACRP-A- 947
   Safety Related Parameters for the MAPLE Research Reactor and a Comparison with the IAEA Generic 10-MW Research Reactor
   P.A. Carlson, A.G. Lee, H.J. Smith, R.J. Ellis

NEACRP-A- 948
   Fuel / Coolant Temperature Coefficient Measurements with (Pu,U)O2 and UO2 Fuel in the ZED-2 Reactor
   R.T. Jones

NEACRP-A- 949
   Critical Heights and Flux Distributions in ZED-2 Reactor for UO2 Reference and (U.Pu)O2 Substitution Cores Employing Air, Water and Heavy Water
   Coolants at Pitches of 24.5 and 31 cm.
   A. Celli

NEACRP-A- 950
   The Use of Enriched Uranium to Modify Coolant Void Reactivity in CANDU
   A.R. Dastur, P.S.W. Chan, S. Girgis

NEACRP-A- 951
   Report on NEANDC Meeting
   27th Meeting , Los Alamos, 26-30 September 1988
   S. Igarasi

NEACRP-A- 952
   Report on NEACRP Specialist's Meeting on Applications of Critical Experiments and Operating Data to Core Design Via Formal Methods of Cross-Section Data Adjustment
   Jackson Hole, September 1988
   D.C. Wade

NEACRP-A- 953
   Proposal of 3-D Neutron Transport Benchmark Problems   (Revision 2)
   January 1989
   T. Takeda, M. Tamitani, H. Unesaki
   Replaces Revision 1 presented at the 31st NEACRP Meeting

NEACRP-A- 954
   Additional Papers on Actinide Monitoring - Physics Aspects from the JRC Ispra
   (presented at the 31st NEACRP Meeting)
   (Copies available from the NEACRP Secretariat)

NEACRP-A- 955
   List of NEACRP Documents, Series A and L.
   17th - 31st NEACRP Meeting
   April 1974 - October 1988
   NEACRP Secretariat

NEACRP-A- 956
   Summary Record of the 10th JEF Scientific Co-ordinating Group Meeting
   Paris, 15 November 1988
   JEF/DOC-262, NEANDC-A-250
   JEF Secretariat

NEACRP-A- 957
   Summary Record of the Twenty-Seventh Meeting of the NEANDC
   Los Alamos, September 1988 (Administrative Minutes)
   NEANDC Secretariat

NEACRP-A- 958
   Summary Record of Twenty-Seventh NEANDC Meeting
   Los Alamos, September 1988 (Technical Minutes)
   Phil Young, LANL

NEACRP-A- 959
   Summary Record of the NEANDC/NEACRP Task Force on Decay Heat Predictions
   London, 21 October 1988
   NEANDC Secretariat

NEACRP-A- 960
   Summary Record of the 31st Meeting of the NEACRP
   (Executive and Technical Sessions)
   O-arai, Japan 17-21 October 1988
   Compiled by F.N. McDonnell
   NEANDC-A-251

NEACRP-A- 961
   TN12 Shipping Cask Calculations Benchmark
   January 1989
   C.M. Diop, J.C. Nimal
   Session B.3.3

NEACRP-A- 962
   High Conversion Light Water Reactor (HCLWR) Burnup Benchmark at Beginning of Life (BOL) and End of Life (EOL) Conditions.
   March 1989
   W. Bernnat, J.Stepanek
   Session B.3.5

NEACRP-A- 963
   Summary Record of the NEANDC/NEACRP Task Force Meeting on International Cooperation in Evaluation
   NEA Secretariat
   Session A.5.1

NEACRP-A- 964
   Nuclear Energy Agency Committee on Reactor Physics
   Summary Record of the Thirty-Second Meeting
   Argonne, 9-13 October 1989
   Executive Session
   F.N. McDONNELL AECL

NEACRP-A- 965
   Review of the Agency's long-term orientations: Contributions from NEA Data Bank
   July 1989
   NEA Secretariat
   Session A.6.3

NEACRP-A- 966
   Summary Record of the 11th meeting of the JEF Scientific Coordination Group,
   Paris, 23rd May 1989.
   NEA Secretariat
   Session A.5.1

NEACRP-A- 967
   Delayed Neutron Branching Ratios of Fission Products
   A Status Report by E. Lund and G. Rudstam,  University of Uppsala, The Studsvik Neutron Research Laboratory
   NFL-60 (1989)
   E. Lund and G. Rudstam

NEACRP-A- 968
   Status of the Noise Analysis Benchmark
   September 1989
   E. Hoogenboom, IRI
   Session B.3.4

NEACRP-A- 969
   Activities of the Committee for Technical and Economic Studies on Nuclear Energy Development and the Fuel Cycle (FCC)
   NEA Secretariat , July 1989
   Session A.5.2

NEACRP-A- 970
   A Consideration on Reactivity Losses in Metal-fueled FBR Cores
   T. Yokoo, M. Kawashima, Y. Tsuboi
   Session B.1.2

NEACRP-A- 971
   Physics Parameters of Advanced Fuel FBR Cores and Evaluation of their Uncertainties
   K. Shirakata, T. Yamamoto, T. Sanda, T. Takeda, N. Uto, M. Yamaoka
   Session B.1.3

NEACRP-A- 972
   Study of the Core Design to use Good Characteristics of New Fuels
   A. Hara, T. Wakabayashi, K. Kinjo
   Session B.1.3

NEACRP-A- 973
   Critical Experiments on Initial Loading Core of Very High Temperature Reactor Critical Assembly (VHTRC)
   F. Akino, T. Yamane, H. Yasuda, Y. Kaneko
   Session B.1.4

NEACRP-A- 974
   Design Study of Graphite Moderated Gas-Cooled High Flux Reactor
   P.H. Liem, H. Sekimoto, E. Suetomi
   Session B.1.4

NEACRP-A- 975
   Fuel Management Effects on the Inherent Safety of Modular High Temperature Reactor
   Y. Hirose, P.H. Liem, E. Suetomi, T. Obara, H. Sekimoto
   Session B.1.4

NEACRP-A- 976
   The Concept of Axially Heterogeneous High Conversion Light Water Reactor
   K. Okumura, Y. Ishiguro, H. Akie, K. Kaneko
   Session B.1.5

NEACRP-A- 977
   Moderator Voidage Effects on Reactor Physics Characteristics of High Conversion Light Water Reactor
   T. Osugi, S. Okajima, M.Obu
   Session B.1.5

NEACRP-A- 978
   Assessment of some Cell Calculation Methods through Analyses of Tight-Pitch Lattice Core Experiments at the KUCA
   S. Shiroya, A. Yamamoto, K. Kanda, T. Takeda
   Session B.1.5

NEACRP-A- 979
   Neutronic Characteristics of a Th/U-233 Fueled High Conversion Light Water Reactor with Axially Heterogeneous Core
   H. Akie, Y. Ishiguro
   Session B.1.5

NEACRP-A- 980
   An Assessment of TRU Recycling Transmutation in Metal Fuel FBR
   A. Sasahara, T. Matsumara
   Session B.2.1

NEACRP-A- 981
   Research of TRU Transmutation System with Proton Accelerator
   T. Nishida, I. Kanno, H. Takeda, Y. Nakahara, S. Yasuda, Y. Kaneko, M. Mizumoto, H. Nakajima, Y. Okumure, M. Sugimoto, T. Takizuka, T. Ogawa, M. Akabori
   Session B.2.1

NEACRP-A- 982
   TRU Transmutation by LMFBR
   T. Wakabayashi, A. Hara, K. Kinjo, T. Kawakita
   Session B.2.1

NEACRP-A- 983
   Three-Dimensional Transport Benchmark
   Japan
   Session B.3.7

NEACRP-A- 984
   NEA Steering Committee for Nuclear Energy
   Trends and Prospects for the Agency: Statement by the Director General
   NE(89)4 March 1989
   NEA
   Session A.6.3

NEACRP-A- 985
   Notes on the Experience with Local and Global Oscillations in the Italian BWRs.
   G. Cannata (ENEL), C. Rita (ENEA)
   September 1989
   Session B.2.3

NEACRP-A- 986
   NEACRP Recommendation for Standard Displacement Damage Dose Unit
   Y. Orechwa (ANL), M. Salvatores (CEA)
   Session A.4

NEACRP-A- 987
   A Proposal for a NEACRP International Comparison of Beta-effective Measurements in MASURCA
   M. Martini, J.C. Gauthier, R. Soule, (CEA)
   Session B.3.8

NEACRP-A- 988
   Analysis of the Possibility to Reduce Sodium Void Reactivity Worth in Large Fast Breeder Reactors
   M. Martini, M. Salvatores (CEA)
   Session B.1.1

NEACRP-A- 989
   Uncertainty Reduction in the Burn-up Reactivity Swing in Fast Breeder Reactors
   M. Salvatores, J.C. Cabrillat, J. Henshall (CEA)
   Session B.1.2

NEACRP-A- 990
   ERASME : An Extensive Experimental Program to Validate the HCLWR Design
   J. P. Chauvin, G. Palmiotti (CEA)
   Session B.1.5

NEACRP-A- 991
   Reactivity Effects and Dynamic Behaviour :
   Comparative Performances of Large LMFBR's Oxide and Metallic Fuel Cores
   Ph. Bergeonneau
   Session B.1.3

NEACRP-A- 992
   Active and Passive N.D.A. Methods for the Characterization of Nuclear Materials
   G. Bignan, L. Martin-Deidier, J. Romeyer Dherbey (CEA)
   Session B.2.4

NEACRP-A- 993
   Status Report on JEF-2 Evaluated Data File
   JEF Secretariat
   Session A.5.1

NEACRP-A- 994
   Analysis of Azimuthal Irregularities in the Flux Distribution on a PWR
   J. Puill (CEA)
   Session B.2.3

NEACRP-A- 995
   NEACRP Thermal Fission Product Benchmark
   September 1989
   M.J. Halsall, C.G. Taubman
   Session B.3.9

NEACRP-A- 996
   Evaluation of Neutron Cross-sections for Liquid Hydrogen and Deuterium for the Design of Cold Neutron Sources
   W. Bernnat, D. Emendoerfer, H.J. Keinert, M. Mattes (IKE)
   Session B.1.6

NEACRP-A- 997
   Calculation of PWR Cycles on the Basis of JEF-1 and ENDF/B-IV-V
   D. Lutz, W. Bernnat
   Session B.1.6

NEACRP-A- 998
   Treatment of Cavities in 3D Diffusion Calculations Based on the Finite Element Method
   W. Bernnat et al. (IKE)
   Session B.1.6

NEACRP-A- 999
   Reduction of Burn-up Reactivity Loss in Large LMFBR Cores by Using Np-237
   S. Pilate, H.W. Wiese
   Session B.1.3

NEACRP-A-1000
   List of NEACRP Technical Topics Discussed from 1975 - 1989
   (18th-32nd NEACRP Meetings)
   NEACRP Secretariat
   Session A.6.2

NEACRP-A-1001
   Overview of the IAEA Reactor Physics Activities 1988/1989
   M. Crijns, IAEA
   Session A.5.2

NEACRP-A-1002
   LEU HTR Critical Experiment Programme for the PROTEUS Facility in Switzerland
   R. Brogli, K.H. Bucher, R. Chawla, K. Foskolos, H. Luchsinger, D. Matthews, G. Sarlos, R. Seiler
   Session B.1.4

NEACRP-A-1003
   Transferability of Information from Driven Critical Experiments to Tight Lattice PWR Design
   J. Kallfelz, L. Belblidia
   Session B.1.5

NEACRP-A-1004
   Status Report on the Intercomparison of Shielding Codes for Transport Flasks. October 1989.
   A. Avery (AEEW)
   Session B.3.3

NEACRP-A-1005
   An Evaluation of LMR Design Options for Reduction of the Sodium Void Worth
   H. Khalil
   Session B.1.1

NEACRP-A-1006
   Fuel Cycle Options for Transuranic-Fueled LMRs
   R. Hill
   Session B.2.1

NEACRP-A-1007
   US Contribution to the International Comparison for Tritium Assaying Methods
   K.G. Porges
   Session B.3.6

NEACRP-A-1008
   ANL Solution to the 3-D Neutron Transport Benchmark Problems
   E. Gelbard, R. Schaefer, P. Collins
   Session B.3.7

NEACRP-A-1009
   A Benchmark for Investigation of the Radial Dependence of the C/E Trends of Control Rod Worths in Large Decoupled Cores
   Y. Orechwa, P. Collins (ANL), M. Salvatores (CEA)
   Session B.3.10

NEACRP-A-1010
   Fuel Processing Data Validation Using the Isotope Correlation Technique
   P.J. Persiani, R.G. Bucher, R.B. Pond, R.J. Cornella
   Session B.2.4

NEACRP-A-1011
   Report of the NEACRP/NEANDC Task Force on Evaluation Co-operation
   BNL, 5-6 October 1989
   J.Rowlands et al.
   Session A.5.1

NEACRP-A-1012
   Activity Report from CSNI, October 1988 - September 1989
   21 September 1989
   CSNI Secretariat
   Session A.5.2

NEACRP-A-1013
   Evaluated Results of the Fuel Nuclides Average Neutron Cross-section Ratio Measurements on the BN-350 Reactor.
   R.K. Goncharov, A.V. Zvonyarov, V.A. Kolyzhenkov, M.N. Nicolev, M.Yu. Semyonov, A.M. Tsibulya
   Session B.1.6

NEACRP-A-1014
   Feasibility of non-Positive Void Reactivity Effect in the Fast Sodium Reactors of Enhanced Self-protection
   I. Slesarev
   Session B.1.1

NEACRP-A-1015
   Calculational Accuracy for Fast Reactor Neutronics Characteristics and their Changes in Burn-up
   G.N. Manturov, M.N. Nikolaev, A.M. Tsyboola
   Session B.1.2

NEACRP-A-1016
   A Small FBR Hexagonal-Z Calculation
   Y.N. Mironovich, A.S. Seregin, I.R. Sooslov
   Session B.3.7

NEACRP-A-1017
   3D Neutron Transport Benchmark Problems - Result of Calculation
   V.I. Bryzgalov, A.D. Rogov, M.S. Yukdevich, V.V. Korobeynikov
   Topic B.3.7

NEACRP-A-1018
   Experimental Investigations on BWR Core and Coolant Channel Flow Stability
   S. Andersson, J. Blomstrand, C. Joensson, ABB Atom
   Session B.2.3

NEACRP-A-1019
   BWR Stability Investigation at Forsmark I
   September 1989
   B.G. Bergdahl, R. Oguma, F. Reisch, G.Lorenzen, F. Akerhielm,
   Studsvik Nuclear
   Session B.2.3

NEACRP-A-1020
   A Proposed Structure for a Shielding Experimental Benchmark Data Bank
   A.K. McCracken (AEEW), E. Sartori (NEADB)
   19 September 1989
   Session B.3.1

NEACRP-A-1021
   International Comparison on Measuring Techniques of Tritium Production Rate for Fusion Neutronics Experiments (Interim Report)
   T. Nakamura (JAERI), H. Maekawa, S. Azam, P.A. Haldy (SFIT)
   Session B.3.6

NEACRP-A-1022
   BWR Stability Analysis (for TVO I)
   September 1989
   K. Valtonen
   Session B.2.3

NEACRP-A-1023
   JRC-Ispra Attempts to Solve the 3D Neutron Benchmark with KENOEUR, September 1989
   H. Rief, M. Gonano, JRC Ispra
   Session B.3.7

NEACRP-A-1024
   Status Report of the NEACRP HCLWR Benchmark Working Group
   October 1989
   W. Bernnat (IKE)
   Session B.3.5

NEACRP-A-1025
   Activity Report from the NEA Data Bank
   October 1988 - September 1989
   NEA DB Secretariat
   Session A.5.2

NEACRP-A-1027
   Voluntary Contribution by the Government of Japan to Reinforce the Agency's Information and R&D Activities in the Field of Nuclear Energy and the Fuel Cycle.
   September 1989
   NEA Secretariat
   Session A.6.3

NEACRP-A-1028
   NEACRP Standard Problem Exercise on Criticality Codes for Dissolving Fissile-Oxides in Acids
   July 1989
   G. E. Whitesides (ORNL)
   Session B.3.2

NEACRP-A-1029
   Understanding the Effect of a Double-heterogeneity on Criticality Calculations and a Method for the Realistic Treatment of the
   Physics of this Problem
   July 1989
   A. Santamarina, H.J. Smith (CEA - Cadarache)
   Session B.3.2

NEACRP-A-1030
   Calculation of the Benchmark 20 of the OECD NEA Working Group on Criticality Calculations
   W. Bernnat, J. Keinert (IKE)
   Session B.3.2

NEACRP-A-1031
   A Comparison of Calculated and Experimental Values of Fine-structure Reaction-rates in CANDU Type Lattices Containing (U_233 Th)O_2 Fuel
   September 1989
   M.B. Zeller, R.T. Jones, A. Celli
   Session B.1.6

NEACRP-A-1032
   The TRIAD3 Code for NRU Reactor Simulation
   September 1989
   M.D. Atfield
   Session B.2.3

NEACRP-A-1033
   Computational Benchmark for Assessment of the Cross-section Files for Shield Design Calculations
   September 1989
   P. Miller, AEEW
   Session A.4

NEACRP-A-1034
   NEACRP 3-D Neutron Transport Benchmark
   September 1989
   H. Ait Abderrahim, G. Minsart
   Session B.3.7

NEACRP-A-1035
   Technical Items for Discussion on Future Developments
   October 1989
   K. Shirakata
   Session A.6.2

NEACRP-A-1036
   Benchmark 3-D Transport Calculations
   September 1989
   L.N. Yaroslavzeva et al.
   Session B.3.7 (in Russian)

NEACRP-A-1037
   The Status of Group Constants Provision for Fast Neutron Reactor Calculations
   September 1989
   M.N. Nicolaev, V.V. Sinitsa, A.M. Tsibulya
   Session B.1.6

NEACRP-A-1038
   Calculational and Experimental Investigations of a Heterogeneous Mock-up on a series of BFS-52 Critical Assemblies
   September 1989
   A.M. Avramov, S.P. Belov, S.B. Bobrov, V.P. Evdokimov, V.F. Efimenko, E.N. Kuzin, V.I. Matveev, I.P. Matveenko, V.A. Tchernyi, B.F. Shafrygin, A.G. Shokodko
   Session B.1.6

NEACRP-A-1039
   Summary Record of the NEACRP/NEANDC Task Force Meeting on Decay Heat Predictions.
   NEA Data Bank, 21-22 September 1989
   NEA Secretariat

NEACRP-A-1040
   Notification of Criticality Working Group Meeting
   2-3 May 1990, Paris Chateau de la Muette
   NEACRP Secretariat
   March 1990

NEACRP-A-1041
   Status of Delayed Neutron Data, 1990
   October 1990
   J. Blachot, M.C. Brady, A. Filip, R.W. Mills, D.R. Weaver
   Draft - circulated to NEACRP members
   To be published as NEACRP-L-323, NEANDC-299U
   Session B 3.8

NEACRP-A-1042
   Summary record of the Second meeting of the Working Group on International Evaluation Cooperation
   Marseille, 30th April - 1st May 1990
   NEA Data Bank Secretariat

NEACRP-A-1043
   Summary Record of the Twelfth Meeting of the Scientific Coordination Group (SCG) of the Joint Evaluated File Project
   OECD, 1st June 1990
   NEA Data Bank Secretariat

NEACRP-A-1044
   The Establishment of a Shielding Experimental Benchmark at the OECD/NEA Data Bank
   June 1990
   A.K. McCRACKEN
   Session B 3.1

NEACRP-A-1045
   Three-dimensional Neutron Transport Benchmark
   Notification of Meeting - 22/23 October 1990, OECD/NEA Data Bank, Saclay
   NEACRP Secretariat

NEACRP-A-1046
   Status of the 1989 Noise Analysis Benchmark Test
   September 1990
   J.E. Hoogenboom
   Session B 3.4

NEACRP-A-1047
   VENUS International Programme (VIP), A Nuclear Data Package for LWR Pu Recycle
   September 1990
   A. Charlier, J. Basselier, L. Leenders
   Session B 1.1

NEACRP-A-1048
   VENUS International Programme (VIP), A Nuclear Data Package for BWR Pu Recycle
   September 1990
   J. Basselier, A. Charlier, P. D'Hondt, L. Leenders, G. Minsart
   Session B 1.1

NEACRP-A-1049
   VENUS International Programme (VIP), A Nuclear Data Package for PWR Pu Recycle
   September 1990
   J. Basselier, A. Charlier, P. D'Hondt, L. Leenders, G. Minsart
   Session B 1.1

NEACRP-A-1050
   Calculation of Neutron-Physical Parameters of the Advanced Light-Water Reactor Fuel Lattices
   September 1990
   V.V. Kuznetsov, A.G. Morozov, A.A. Dudnikov, I.S. Slesarev
   Session B 2.2

NEACRP-A-1052
   The Cold Neutron Moderator for the Continuous Spallation Neutron Source SINQ
   March 1990
   F. Atchison, G. Bauer, W. Fischer, K. Skala, H. Spitzer
   Session B 1.4

NEACRP-A-1053
   On the Effect of ENDF/B-VI Beryllium Data on the Neutronics of ITER Blankets
   September 1990
   Sandro Pelloni, Mark J. Embrechts, Edward T. Cheng
   Session B 1.5

NEACRP-A-1054
   Reduction of the Long-Term Toxicity of Neptunium by Nuclear Spallation
   September 1990
   H.U. Wenger, P. Wydler, S. Atchison
   Session B 2.3

NEACRP-A-1055
   Plutonium Reload Experience and Perspective in French PWR Plants
   October 1990
   M. Rome, M. Salvatores, J. Mondot, M. Le Bars
   Session B 1.1

NEACRP-A-1056
   Quality Assurance Provisions for ERANOS
   October 1990
   J.M. Rieunier, G. Palmiotti
   Session B 1.2

NEACRP-A-1057
   Comparative Study of the Neutronic Performances of a Large LMFBR Using Oxide Fuel or Metallic Fuel
   October 1990
   J.C. Garnier, A. Zaetta
   Session B 1.3

NEACRP-A-1058
   Sodium-Voiding Reactivity Effect Reduction in Fast Breeder Reactors
   October 1990
   J. Thommasi, A. Zaetta
   Session B 1.3

NEACRP-A-1059
   Modular Island Cores
   October 1990
   C. De Pascale, A. Zaetta
   Session B 1.3

NEACRP-A-1060
   Sensitivities Analysis of the T.F. Coil Shielding Parameters in the NET Design to the Nuclear Data Uncertainties
   October 1990
   A. Santamarina, H. Smith
   Session B 1.5

NEACRP-A-1061
   Reactor Physics Studies at CEA on Advanced Water Reactors
   October 1990
   A. Leridon et al.
   Session B 2.2

NEACRP-A-1062
   Radiotoxicity of Wastes Impact of Plutonium Recycling
   October 1990
   M. Darrouzet, G. Flamenbaum, J.P. Grouiller
   Session B 2.3

NEACRP-A-1063
   Active and Passive Non-Destructive Measurements for Nuclear Monitoring of Spent Assemblies
   October 1990
   G. Bignan, L. Martin-Deidier
   Session B 2.5

NEACRP-A-1064
   NEACRP Beta-effective Benchmark Measurements at MASURCA. Proposal for the Experimental Program
   October 1990
   M. Martini, J.C. Gauthier, G. Granget, R. Soule
   Session B 3.8

NEACRP-A-1065
   Proposal for Benchmark Calculations of Power Distribution within an Assembly using Standard or Nodal Diffusion Schemes
   October 1990
   J.C. Lefebvre, J. Mondot, J.P. West and al.
   Session B 3.10

NEACRP-A-1066
   Plutonium Generation Boiling Water Reactor Concept
   October 1990
   Renzou Takeda, Motoo Aoyama, Yoshihiko Ishii, Osamu Yokomizo, Kazuya Ishii, Noriyuki Sadaoka, Sadao Uchikawa
   Session B 1.1

NEACRP-A-1067
   Utilization of MOX Fuel Assembly Containing Gd2O3 in ATR
   October 1990
   Norio Kawata, Toshio Wakabayashi
   Session B 1.1

NEACRP-A-1068
   Study of Enhanced Safety Core Characteristics of Nitride Fuel FBR
   October 1990
   Y. Ohkubo, T. Wakabayashi
   Session B 1.3

NEACRP-A-1069
   Integral Experiments to Improve Tritium Breeding Ratio
   October 1990
   Akito Takahashi, Ken Yamanaka, Kenji Sumita
   Session B 1.5

NEACRP-A-1070
   Phase-IIIA Experiment of the JAERI/USDOE Collaborative Program on Fusion Neutronics
   October 1990
   Y. Oyama, C. Konno, Y. Ikeda, H. Maekawa, K. Kosako, T. Nakamura
   Session B 1.5

NEACRP-A-1071
   Benchmark Test of Be Nuclear Data in JENDL-3 Through Analyses of Time-of-Flight and Integral Experiments on Be Assemblies at FNS
   October 1990
   Hiroshi Maekawa, Yukio Oyama, Kazuaki Kosako
   Session B 1.5

NEACRP-A-1027
   Prediction Accuracies of Safety Related Core Design Parameters for FBR
   October 1990
   Keisho Shirakata, Toshio Sanda
   Session B 2.1

NEACRP-A-1073
   Measurement of Void Reactivity Worth of HTTR Mockup Control Rod Hole in VHTRC-1 Core
   October 1990
   F. Akino,T. Yamane, M. Takeuchi, Y. Kaneko
   Session B 2.2

NEACRP-A-1074
   Analysis of Temperature Effect of Reactivity for VHTRC and SHE with Nuclear Design Code System for High Temperature Engineering Test Reactor (HTTR)
   October 1990
   Isao Murata, Kiyonobu Yamashita, Ryuichi Shindo
   Session B 2.2

NEACRP-A-1075
   Study of TRU Transmutation Plant with Proton Accelerator
   October 1990
   T. Nishida, I. Kanno, H. Takada, T. Takizuka, M. Mizumoto, M. Akabori, Y. Nakahara, Y. Okumura, H. Yasuda, Y. Kaneko
   Session B 2.3

NEACRP-A-1076
   TRU Transmutation in an LMFBR
   October 1990
   M. Ishikawa, M. Yamaoka, T. Wakabayashi, T. Kawakita
   Session B 2.3

NEACRP-A-1077
   A Study of Regional Oscillation with TOSDYN-2
   October 1990
   Y. Takigawa, Y. Takeuchi, H. Namba, S. Ebata,
   S. Kasai, T. Anegawa
   Session B 2.4

NEACRP-A-1078
   Examination of Nuclear Thermal Hydraulic Oscillation Modes in BWR Core.
   October 1990
   O. Yokomizo, I. Sumida, T. Anegawa, Y. Yoshimoto, T. Fukahori
   Session B 2.4

NEACRP-A-1079
   Development of Non-Destructive Measuring Techniques for Trace Amount of Fissile and Fertile Materials in Drum-Sized Waste
   October 1990
   H. Gotoh, M. Haruyama, N. Wakayama
   Session B 2.5

NEACRP-A-1080
   International Comparison on Measuring Techniques of Tritium Production Rate for Fusion Neutronics Experiments
   October 1990
   Summarized by Hiroshi Maekawa
   Session B 3.6

NEACRP-A-1081
   Progress Report on 3-D Neutron Transport Benchmark Problems
   October 1990
   T. Takeda, H. Ikeda, M. Tamitani
   Session B 3.7

NEACRP-A-1082
   Viewgraphs on the Activities of the Committee on the Safety of Nuclear Installations (CSNI)
   October 1990
   CSNI Secretariat
   Session B 4.1

NEACRP-A-1083
   Summary of Activities of the Nuclear Development Committee (NDC)
   October 1990
   NDC Secretariat
   Session B 4.1

NEACRP-A-1084
   Quality Assurance (QA) for Neutronics Codes at ANL
   October 1990
   ALN Secretariat
   Session B 1.2

NEACRP-A-1085
   Requirements for Validating (LWR) Neutronics Codes
   October 1990
   David J. Diamond
   Session B 1.2

NEACRP-A-1086
   A Measurement Based Method for Predicting Margins and Uncertainties for Unprotected Accidents in the Integral
   Fast Reactor (IFR)
   R.B. Vilim
   Session B 1.3

NEACRP-A-1087
   High Neutron Flux Fusion Materials Test Facility
   L.G. LeSage
   Session B 1.4

NEACRP-A-1088
   Sensitivity/Uncertainties Analyses for Fusion Applications
   September 1990
   ANL Secretariat
   Session B 1.5

NEACRP-A-1089
   Pin Power and Depletion in EBR-II
   October 1990
   W.S. Yang, R.D. McKnight
   Session B 2.1

NEACRP-A-1090
   Hazard Quantification for LWR Spent Fuel
   October 1990
   R. N. Hill
   Session B 2.3

NEACRP-A-1091
   A Review of Reactor Physics Uncertainties and Validation Requirements for the Modular High-Temperature Gas-Cooled Reactor
   May 1990
   A.M. Baxter, R.K. Lane, E. Hettergott, W. Lefler (General Atomics)
   Session B 1.2

NEACRP-A-1092
   Reaction Rate Distributions and Related Data in the FNS Phase II Experiments: Comparison of Measured and Calculated Data
   July 1990
   R.T. Santoro, R.G. Alsmiller, Jr., J.M. Barnes (ORNL)
   Session B 1.5

NEACRP-A-1093
   Considerations for a Shielding Experimental Benchmark Data Base
   October 1990
   W.W. Engle, Jr., D.T. Ingersoll (ORNL)
   Session B 3.1

NEACRP-A-1096
   Licencing Safety Critical Software. Public Opinion and the Full Power of the Mind.
   G.H. Archinoff, R.A. Brown.
   Hans Y. Tammemagi
   Session B 1.2

NEACRP-A-1098
   Neutronic Decoupling and Coolant Void Reactivity in CANDU
   September 1990
   V.K. Mohindra, A.R. Dastur
   Session B 2.4

NEACRP-A-1099
   SMOKIN - A Code for Time-Dependent Three-Dimensional Neutronics Calculations in CANDU-PHW Reactors Based on Modal Kinetics Theory - Application to loss-of-coolant accidents
   September 1990
   M. Gold, J.C. Luxat
   Session B 2.4

NEACRP-A-1100
   28th NEANDC meeting: Report on matters of interest to NEACRP
   October 1990
   E. Fort
   Session B 4.1

NEACRP-A-1101
   ANITA - Analysis of Neutron Induced Transmutation and Activation
   April 1990
   C. Ponti, S. Stramaccia, (JRC Ispra)
   Session B 1.5

NEACRP-A-1102
   BWR Stability Investigation in Ringhals 1. Measurement Data from October 26, 1989
   (Summary of Studsvik Report NI-90/17)
   October 1990
   Bengt-Goeran Bergdahl, Ritsuo Oguma
   Session B 2.4

NEACRP-A-1103
   PHYSOR'90: Conference Summary
   May 1990
   John L. Rowlands
   Session B 5.1

NEACRP-A-1104
   Summary Record of the Twenty-eighth NEANDC Meeting
   Harwell, 26-30 March 1990, (Technical Minutes)
   Herbert Vonach, IRK
   Session B 4.1

NEACRP-A-1105
   Overview of the IAEA Reactor Physics Activities 1989/1990
   October 1990
   M. Crijns, IAEA
   Session B 4.1

NEACRP-A-1106
   Activity Report of the OECD/NEA Data Bank for the NEACRP Meeting
   October 1990
   NEA Data Bank Secretariat
   Session B 4.1

NEACRP-A-1107
   Status Report on the Intercomparison of Shielding Codes for Transport Flasks
   October 1990
   A. F. Avery
   Session B 3.3

NEACRP-A-1108
   Status Report of the NEACRP HCLWR Benchmark Working Group
   October 1990
   W. Bernnat, E. Sartori
   Session B 3.5

NEACRP-A-1109
   On Actinides Transmutation Possibility in Fast Reactors with Various Coolants
   October 1990
   D.F. Tzurickov, A.N. Shmelyov, A.G. Morozov, V.B. Glebov, G.G. Koulickov, V.V. Kuznetzov
   Session B 2.3

NEACRP-A-1110
   Experimental and Calculational Investigation on HCLWR Physics
   October 1990
   IPPE, Obninsk and IAE, Moscow Secretariats
   Session B 2.2

NEACRP-A-1111
   Sensitivities to Nuclear Constants and Related Calculational Errors in Safety Characteristics of Fast Reactors with
   Different Coolants
   October 1990
   G.G. Kulikov, V.B. Glebov, A.G. Morozov, I.V. Kurchatov
   Session B 1.3

NEACRP-A-1112
   Investigations for Design Justification of Actinides Transmutation Reactor. On Actinides Transmutation Possibility in Fast Reactors with Various Coolants.
   October 1990
   S.M. Bednyakov, V.A. Dulin, L.V. Korobeinikova, G.N. Manturov, I.P. Matveenko, A.M. Tsibulya / D.F. Tzurickov, A.N. Shmelyov, A.G. Morozov, V.B. Glebov, G.G. Koulickov, V.V. Kuznetzov
   Session B 2.3

NEACRP-A-1113
   Fusion Blanket Benchmark Experiments
   October 1990
   V.V. Afanasiev, A.G. Belevitin, Y.M. Verzilov, V.L. Romodanov, V.V. Khromov, D.V. Markovshij, G.E. Shatalov
   Session B 1.5

NEACRP-A-1114
   Activity Report of the Criticality Working Group
   October 1990
   G. Elliott Whitesides, E. Sartori
   Session B 3.2

NEACRP-A-1115
   Analysis of JOYO Burnup Characteristics
   October 1990
   Akihiro Hara, Kastuya Kinjo
   Session B 2.1

NEACRP-A-1116
   Investigations on Pu-Recycling and High Burnup for LWRs in the Federal Republic of Germany
   F.U. Schlemmer, G.J. Schlosser, W.D. Krebs, H.P. Fuchs, R. Manzel,
   H.W. Wiese
   Session B 1.1

NEACRP-A-1117
   Benchmark 3-D Neutron Transport Calculations
   October 1990
   L.N. Yaroslavtseva, P.A. Fomichenko, L.L. Kononova
   Session B 3.7

NEACRP-A-1118
   3-D neutron Transport Benchmark Problems
   October 1990
   V.I. Bryzgalov, V.V. Korobeiynikov, A.D. Rogov, M.S. Yudkevich
   Session B 3.7

NEACRP-A-1119
   Benchmark Calculations of Power Distribution Within Assemblies
   J.C. Lefebvre (EDF/SEPTEN), J. Mondot (CEA/DRN/DER), J.P. West (EDF/DPT/SPT)

NEACRP-A-1120
   Summary of the first meeting on Experimental Program of NEACRP Beta-effective Benchmark Measurement at MASURCA
   Held at Cadarache on 4-5th December 1990
   M. Martini, CEA Cadarache
   January 1991

NEACRP-A-1121
   Summary Record of 33rd NEACRP Meeting (Executive and Technical Sessions)
   OECD/NEA Paris, 15-19 October 1990
   NEANDC-A-302
   R. Martinelli

NEACRP-A-1122
   Summary Record of the 3rd Meeting of the Working Group on International Evaluation Cooperation.
   NEANDC-A-303
   NEA Secretariat
   June 1991

NEACRP-A-1123
   Summary Record of the 13th Meeting of the Scientific Coordination Group of the JEF Project.
   JEF/DOC-353
   NEANDC-A-304
   NEA Secretariat

NEACRP-A-1124
   Notification of Criticality Calculations Working Group Meeting
   Christchurch College, Oxford, UK, 11 September 1991, 20:30
   NEACRP Secretariat

NEACRP-A-1125
   Overview of the IAEA Reactor Physics Activities 1990/91
   September 1991
   M. Crijns, IAEA

NEACRP-A-1126
   Some Preliminary Remarks concerning the Proposal of an International Benchmark on Variance Reduction Schemes Employed in Monte Carlo Neutron and Photon Transport Codes.
   April 1991.
   K.W. Burn, ENEA

NEACRP-A-1127
   Report from the Criticality Calculations Working Group
   August 1991
   E. Sartori

NEACRP-A-1128
   Report from CSNI and CNRA
   August 1991
   D. McPherson, OECD/NEA

NEACRP-A-1129
   Nuclear Development Committee (NDC) - Work Programme
   August 1991
   G. Stevens, OECD/NEA

NEACRP-A-1130
   Activity Report of the OECD/NEA Data Bank for NEACRP, August 1991
   NEA Data Bank Secretariat

NEACRP-A-1131
   Shipping Cask Shielding Benchmarks
   Status Report, September 1991
   E. Sartori, OECD/NEA

NEACRP-A-1133
   Validation of the Reactor Dynamics Code TRAB
   H. Raeti, R. Kyrki-Rajamaeki, M. Rajamaeki
   VTT

NEACRP-A-1134
   NEACRP 3-D LWR Core Transient Benchmark - Draft Specifications
   H. Finnemann SIEMENS/KWU, A. Galati ENEA/CRE

NEACRP-A-1135
   Report on NEANDC Activities to the 34th NEACRP Meeting
   Sept. 1991
   H. Conde' Uppsala University

NEACRP-A-1136
   Draft Terms of Reference for the Nuclear Science Committee and an Executive Group
   10 July 1991
   NEA Secretariat

NEACRP-A-1137
   NEACRP Summary Record of Thirty-fourth Meeting
   PSI Villigen, 3-5 September 1991
   R. Martinelli

NEACRP-A-1138
   Summary Record of 29th NEANDC Meeting
   Karlsruhe, 21-25 October 1991
   NEANDC-A-310
   NEA Secretariat