Index to unrestricted NEA/NEACRP/L Documents

Raievski, V., The Physics of ORGEL Reactors, (DPR-170), June 1962
Raievski, V., The ECO Reactor, (DPR-174), June 1962
Naudet, R., Etudes sur la Physique des Reseaux a Eau Lourde, June 1962
Naudet, R., Calcul des Sections Efficaces effectives dans les Reacteurs Thermiques, June 1962
Summary of Reactor Physics Work in Norway relevant to the Special Topics for the EACRP Meeting in Saclay, June 1962
Pershagen, B., Summary of Theoretical Work on Heavy Water Lattices in Sweden, June 1962
Leslie, D.C. and Poole, M.J., Thermal Neutron Spectra in Reactors, (NP/Gen/27), June 1962
Crandall, J.L., Status of the United States Effort in D2O Reactor Physics, June 1962
Spinrad, B.I., Status of Work in the United States of America on Reactor Spectra, June 1962
List of Subcritical Facilities, October 1962
List of Research Reactors and Critical Facilities, November 1962
Kalnaes, O., Neltrup, H. and Olggard, P.L., The Present Danish Recipe for D20 Lattice Calculations, January 1963
Vilstrup, H. (Editor): Reactor Physics; Abstracts of Programmes, February 1963
Askew, J.R. and Tyror, J.C., Problems Involved in Cell Burnup Calculations for Thermal Reactors, (AEEW Memo 321), February 1963
Blomberg, P.E., Reactor Physical Studies of the Burnup Effects in the R3 Reactor, February 1963
Persson, R., Perturbation Analysis Applied to Substitution Measurements of Buckling, February 1963
Ager-Hanssen, H., Reactor Physics Experience Obtained from the Experimental Operation of the Halden Heavy Water Boiling Reactor, (Abstract), January 1963
Ortiz Fornaguera, R., On the Role of Small Computers in Nuclear Reactor Calculations, January 1963
Butler, M., Report on Argonne Code Center, January 1963
Avery, R., Burn-Up Physics of Thermal Reactors, February 1964
Baumann, N.P., Resonance Integrals and Self-Shielding Factors for Detector Foils, (DP-817), January 1963
Graves, W.E., Analysis of Substitution Measurements, January 1963
Driggers, F.E., BSQ - An IBM-704 Code to Calculate Heavy Water Lattice Parameters, February 1963
Technical Minutes of the Second Meeting, Zurich, 11-14 February 1963, June 1963
Norbury, J. and Mossop, I.A., Non-destructive Measurement of Power, Burn-up and their Distributions in Irradiated Fuel, (W 5955), September 1963
Jakeman, D. and Maunders, E.J., The Use of Iridium Foils for the Measurement of the Pu240 Resonance Escape Probability in Plutonium Fuelled Reactor Assemblies, (W 5958), September 1963
Codd, J. and Collings, P.J., Some Calculations concerning the Influence of Resonane Overlapping on the Doppler Effect in a Dilute Fast Reactor, (W 5960), September 1963
Skillings, D.J., Methods of Conversion Ratio Measurement, (W 5954), September 1963
Hitchcock, A.J.M., Operational Problems of Burn-up, (W 5954A), October 1963
Hansson, L., Reactor Physics Abstracts of Programs, October 1963
Tyror, J.C., The Doppler Coefficient in Thermal Reactors, (W 5967), October 1963
Naudet, R., Examen Critique des Methodes de Substitution, October 1963
Boeuf, A. and Tassan, S., A Measurement of the Fine Structure of the Thermal Flux in Simple-Geometry ORGEL Type Lattices, (EUR 206 e.), F ebruary 1963
Blasser, G., Doppler-Effect in Heterogeneous Lattices for Parabolic Temperature Distribution in the Fuel, (DPR-158), May 1962
Raievski, V., Reactor Physics Program at Euratom CCR-ISPRA, (DPR-323), September 1963
Casini, G., and Megier, J., Critical Analysis of the Progressive Substitution Method for Material Buckling Measurements, August 1963
Johansson, E., Jonsson, E., Lindberg, M. and Mednis, J., The Neutron Spectrum in a Uranium Tube, (AE-123), October 1963
Andersen, E., A Survey of Recent Activities in Reactor Physics at the Kjeller Research Establishment, October 1963
A Survey of Recent Activities in Reactor Physics in Sweden, October 1963
Saussure, G. de, Weston, L.W., Gwin R., Russel, J.E. and Hockenbury, R.W., Measurement of alpha for U235 in the Energy Region from 4 eV to 2 keV, October 1963
D20 Lattice Data, September 1970 Supplement)
Kouts, H. and Avery, R., EACRP Sub-Committee Report on Neutron Cross Sections, October 1963
Paratte, J.M. and Etemad, A., Neutron Flux Measurements in Bent Air Ducts through Water, January 1965
Hicks, D., Reactor Calculation Models for Burn-up Studies, (W6067), September 1963
Technical Minutes of the Third Meeting, Idaho Falls, 21st-25th October 1963, March 1964
Kalnaes, O., Neltrup, H. and Olgaard, P.L., A receipe for heavy water lattie calculations, May 1964
Ortiz Fornaguera, R., On the Derivation of Conventional Neutron Kinetic Equations, June 1964
Ager-Hanssen, H. and Smith, R.D., New HBWR Programme Aims at Improved BWR Performance, January 1964
Naudet, R. and Tretiakovv, O., Incidence des Progres Recents en Theorie de la Thermalisation sur la Physique des Reacteurs, April 1963
Technical Minutes of the Fourth Meeting, Hankoe, 15th-17th June 1964, November 1964
Jones, R.H. (Editor), A Compilation of Experimental and Theoretical Neutron Spectra, (AERE-R-4776), November 1964
Shielding Activities, Euratom, Ispra, January 1965
Naudet, R. and Tretiakoff, O., Analyse Isotopique des Combustibles Irradies - Remarques Generales sur les Programmes et les Methodes, January 1965
Smets, H.B., Reactor Core Dynamics, March 1965
Tehnical Minutes of the Fifth Meeting, Madesimo, 18th-22nd January 1965
Hirota, J., Reactor Physics Activities in Japan, September 1965
Technical Publications by JAERI Staff through 1964, (JAERI-5011, Vol. 1), September 1965
Rapport d'activite en Physiques des Reacteurs - (France), Extrait de: Progress Report on Nuclear Data Research in the Euratom Community, July 1963-December 1964, (EANDC(E)57"U"), December 1965
Kuchle, M., Pulsed Neutron Research - Highlights from the IAEA Symposium, Karlsruhe, 10th-14th May 1965
Technical Minutes of the Sixth Meeting, Montreal, 4th-7th October 1965, April 1966
Neutron Spectra, September 1966
Supplement 1: Dec. 1966;
Supplement 2: Fev, 1967;
Supplement 3: Oct. 1968;
Supplement 4: August 1970;
Supplement 5: January 1972.
Reactor Physics in OECD Countries, October 1965-June 1966, March 1967
Hirota, J., Reactor Physics Activities in Japan, Period October 1965 to May 1966, 6th June 1966
Reactor Physics in OECD Countries, June 1966-February 1967, June 1967
Reactor Physics in OECD Countries, February-September 1967, January 1969
Kuroi, H., Mitani, H., Ishiguro, Y., Mizoo, N., Takano, H., and Hirota, J.: Parametric Survey of Uncertainty in the Group Constant for the Resonance Energy Region for U235, U238 and Pu239, 1967
Inoue, K., Scattering Process Approach to Neutron Spectrum in Fast Reactors
Reactor Physics in OECD Countries, October 1967-May 1968
Reactor Physics Activities in OECD Countries, June 1968-January 1969
Reactor Physics in OECD Countries, February 19690October 1969
Naudet, R., Analyse des formalismes de la theorie heterogene, Decembre 1968
Kuchle, M. and Wattecamps, E., Proposal for a Standard Spectrum to Check Techniques of Fast Spectrum to Check Techniques of Fast Neutron Spectrum Measurements, February 1969
Tiren, T.I., Activation Doppler Measurements, February 1969
Buccari, G., Fattori, G., and Mongini-Tamagnini, C., Linked Calculations - Caronte Project
Kallfelz, J.M., Zolotar, B.A. and Sehgal, B.R., Modifications to Fissile Element Cross-Sections and their Influence on Calculated Fast Reactor Parameters
Reactor Physics Activities in OECD Countries, November 1969-June 1971
Reactor Physics Activities in OECD Countries, June 1970-June 1971
Reactor Physics Activities in OECD Countries, June 1971-June 1972
Report on the File Format Working Group Meeting (Bologna, 7th-9th June 1972), ed. by G.C. Panini
Sanders, J.E. and Stevenson, J.M., A Comparison of reactivity scales in a fast critical assembly, June 1973
Vincenti, E., Forti, G., Clusaz, A. and Dal Ben, S., Space - Dependent Reactor Dynamics, 29th April 1973
a. Struwe, D., RADYVAR2 - A two-dimensional accident analysis code for LMFBR with space dependent feedback
b. Mayer, L. The quasi-static approach KINTIC
c. Terney, W.B. and Srivenkatesan, R., Fast Reactor Transient Analysis with Synthesis and few Groups models
d. Birkhofer, A. and Werner, W., Fully implicit matrix decomposition method for space-time kinetics
Miyasaka, F.C., Studies of sensitivity of shield performance to nuclear data variations, May 1973
Weisbin, C.R. and La Bauve, R.J., Specification of a generally useful multigroup structure for neutron transport
Campbell, C.G. and Rowlands, J.L., The production and performance of the adjusted cross-section sets FGL5 and FD5, June 1973
Gandini, A., Petilli, N. and Salvatores, M., Multigroup cross-sections evaluations at CNEN using integral data and statistical adjustment techniques
Taji, Y., Miyasaka, S., Hirota, J., Inoue, S., Ideta T., Asaoka, T. and Katsuragi, S., Analysis of Energy Deposition due to Neutron and Gamma Rays, May 1973
Reactor Physics Activities in OECD Countries, June 1972-May 1973 (16 reports in total)
Andersson, G., Edenius, M., Hellstrand, E. and Persson, R., Comparison between Predicted and Measured Temperature Coefficients of Reactivity in some Light Water Lattices
Summary of Finite Element Exchange, May 1973
Summary Report of the Meeting on Void Coefficients held in Paris, 18th-20th September 1972
Smith, R.W., Some Observations on the Comparison of Measured and Calculated Small Sample Reactivity Worths of Fissile Isotopes in Fast Integral Assemblies, 28th June 1972
Rowlands, J.L., and Sanders, J.E., Fast Reactor Spectrum Measurements and their Application to Data Adjustment Studies, June 1972
Griggs, C.F. and Halsall, M.J., Trans-Plutonium Elements in Thermal Reactors, 27th June 1972
Fisher, E.A., Kilian, P. and Kusters, H., Prediction of Void Coefficients in Fast and Thermal Reactors, June 1972
Bohn, E.M., The Central Worth Discrepancy, 1st June 1972
Butler, J., Carter, M.D., McCracken, A.K. and Packwood, A., The UK Programme of DATAM Experiments on Energy-Deposition and Radiation Penetration, April 1974
Knipe, A.D., A TLD Benchmark Experiment with a Cobalt-60 Source in Iron, April 1974
McCracken, A.K., The RADAK Unfolding Code, April 1974
Summary Record of the Sixteenth EACRP Meeting, Chicago, USA, 4th-8th June 1973 (Technical Sessions), compiled by E. Hellstrand
Maerker, R.E. and Muckenthaler, F.J., Final Report on a Benchmark Experiment for Neutron Transport through Iron and Stainless Steel (ORNL-4892), April 1974
Maerker, R.E., et al., Final Report on a Benchmark Experiment for Neutron Transport in Thick Sodium
Cross Section Requirements for Threshold Detectors
Magurno B.A.
May 1974
McFarlane, H.F., Linebrry, M.J., Goin, R.W., Kaiser, R.E. and Beck, C.L., Small Sample Measurements in ZPPR Assembly 3
Lineberry, M.J., Beck, C.L., Amundson, P.I., Simons, G.G. and Olson, P.N., The Present Status of Comparisons of Sodium Void Calculations and Measurements from the Critical Experiments Program, 1st June 1974
Recent EBR-II Experience, June 1974
Cox, S.A., Delayed Neutron Data - Review and Evaluation, June 1974
Reactor Physics Activities in OECD Countries, June 1973 - May 1974
NEA/NEACRP/L(1974)112Shielding Benchmark Experiments - Report of a Joint NEA/EURATOM
Meeting held at Ispra on 17th-19th April 1974
Butler, J. and Nicks, R.
May 1974
NEA/NEACRP/L(1974)113Available Reactor Physics Data from Power Reactors - Material Utilized by the
Reactor Physics Section at Risoe (RP-2-74)
T. Pertersen
May 1974
NEA/NEACRP/L(1974)114Thermal Benchmark Experiment Compilation
G. Casini
May 1974
NEA/NEACRP/L(1974)115Measurements of the Adjoint Flux in a Compact Fast Reactor
Bozzi, L., Martini, M. and Matteucci, R.
May 1974
NEA/NEACRP/L(1974)116The Use of the Stacey Algorithm to Improve the Elastic Moderation Cross-Section Generation
Palmiotti, G. and Salvatores, M.
NEA/NEACRP/L(1974)117Error Files and the Consistent Method
Gandini, A. and Salvatores, M.
NEA/NEACRP/L(1974)118Proceedings of the NEACRP Meeting of a Monte Carlo Study Group at Argonne
National Laboratory (ANL-75-2)
1st-3rd July 1974
NEA/NEACRP/L(1974)119Summary Record of the Seventeenth Meeting of the NEACRP (Technical Sessions)
Cadarache (France)
E. Hellstrand
4th-7th June 1974
NEA/NEACRP/L(1974)120Reactor Physics Activities in OECD Countries
May 1974 , May 1975
NEA/NEACRP/L(1975)121The NEA/Euratom Restricted Meeting of Specialists on Shielding Benchmark Experiments held at AEE, Winfrith; April 1975; Summary Report prepared for the NEA-CRP Meeting to be held at Bologna
Butler, J. and McCraken, A.K.
9th-13th June 1975
NEA/NEACRP/L(1975)122Breeding Performing of Carbide and Nitride Fuels in 5000 MWth LMFBRs
NEA/NEACRP/L(1975)123Measurement of the Breeding Ratio and Its Components in ZPPR Assembly 4 Phase I
NEA/NEACRP/L(1975)124ZPPR Assembly 3 Control Rod Worth Measurements
Simons, G.G.
NEA/NEACRP/L(1975)125Streaming and Leakage Problems in Fast Reactors
Langlet, G. and Khairallah, A.
6th June 1975
NEA/NEACRP/L(1975)127Neutron Streaming in Fast Critical Assemblies
Wade, D.C. and Gelbard, E.M.
NEA/NEACRP/L(1975)128Analysis of Measurements in the Null Reactivity Zone in ZPR-9/25 and Comparisons with the SCHERZO 556 Medium
NEA/NEACRP/L(1975)129Comparison of Reaction Rate Ratio Measurements in ZPPR and in ZEBRA Assembly 12 (MZB)
Collins, P.J. and Beck, C.L.
NEA/NEACRP/L(1975)130Time-Dependent Generalized Perturbation Methods for Burn-Up Analysis
Gandini, A.
NEA/NEACRP/L(1975)131Assessment Studies for Actinides Waste
Schmidt, E.
June 1975
NEA/NEACRP/L(1975)132Actinide Fission Rate Measurements in ZEBRA 14
Sweet, D.W.
4th June 1975
NEA/NEACRP/L(1975)133Cycle Design and Fuel Management for a PWR
NEA/NEACRP/L(1975)134The IBUS2-SELMA2 Fuel Management System (Risoe Report No. 310)
Weber, S.
September 1974
NEA/NEACRP/L(1975)135Nuclear Blanket and Shielding Problems in Demonstration Fusion Reactors
Casini, G. and Cuniberti, R.
NEA/NEACRP/L(1975)136Analysis of Fission Ratio Distribution in Spherical Lithium Metal Assembly with a Graphite Reflector
Seki, Y., Maekaa, H., Moriyama, M., Hiraoka, T. and Hirota, J.
NEA/NEACRP/L(1975)137Calculation of Observable Streaming Effects in GCFR Lattices
McCombie, C.
June 1975
NEA/NEACRP/L(1975)1382D IAEA Benchmark Problem (DAEK-RP-3-75)
Misfeldt, I.
4th June 1975
NEA/NEACRP/L(1975)1393D IAEA Benchmark Problem 2nd Order FEM Calculation (DAEK-RP-4-75)
Misfeldt, I.
4th June 1975
NEA/NEACRP/L(1975)140Fission-Neutron Spectra: Brief Review and Status of the Long-Standing Inconsistencies between Differential and Integral Data
Fabry, A.
NEA/NEACRP/L(1975)141Experimental Determination of Integral Capture Cross-Sections of Structural Materials in Fast Spectra, Progress Report to April 1975
Tassan, S.
15th May 1975
NEA/NEACRP/L(1975)1423D IAEA Benchmark Problem 3rd Order FEM Calculation (DAEK-RP-5-75)
Misfeldt, I.
6th June 1975
NEA/NEACRP/L(1975)143A Fuel Management Study and Cycle Nuclear Design for PWR Reactors
Minguez E. et Al.
NEA/NEACRP/L(1975)144Summary Record of the Eighteenth Meeting of the NEA-CRP (Technical Sessions) Bologna (Italy)
Richmond, R.
9th-13th June 1975
NEA/NEACRP/L(1975)149Investigation of the Accuracy of Counterpoint, Cornerpoint and Finite Element Methods of the Diffusion Equation
G.K. Kristiansen
NEA/NEACRP/L(1975)150Summary Report on the Specialists Meeting on Sensitivity Studies and Shielding Benchmarks
October 1975
NEA/NEACRP/L(1975)151PWR Benchmark Specifications
Hehn & Koban
NEA/NEACRP/L(1975)152Fast Reactor Shielding Benchmark
J.Y. Barre
NEA/NEACRP/L(1975)153Technical Minutes of 18th Meeting of the Committee Bologna (Italy)
9 - 13 June 1975
NEA/NEACRP/L(1976)155Reactor Physics Activities in OECD Countries, 1976
NEA/NEACRP/L(1976)160Review of Physics Problems related to Fast Reactor Safety (France)
A. Khairallah 1976
NEA/NEACRP/L(1976)161Specialists' Meeting on Control Rod Measurement Techniques. Reactivity Worth and Power Distribution (France)
J.Y. Barre
NEA/NEACRP/L(1976)162The Analysis of Control Rod Experiments in Zebra Core 12 and Implications for Power Reactor Calculations (UK)
A.M. Broomfield, M.D. Carter, P.J. Collins, J. Marshall, J.L. Rowlands
NEA/NEACRP/L(1976)165Response Distributions of 6LiF and 7LiF Thermo-luminescense Dosimeters in Lithium Blanket Assemblies (Japan)
H. Maekawa, J. Kusane, Y. Seki
NEA/NEACRP/L(1976)166Neutronics of Laser Fission-Fusion Systems (Spain)
NEA/NEACRP/L(1976)167Fast Reactor Benchmark Problem (parts a,b) (Germany)
NEA/NEACRP/L(1976)169Near Breeding Thorium Fuel Cycle in the PEBBLE BED HTR (Germany)
E. Teuchert, H.J. Rutten
NEA/NEACRP/L(1976)170Homogenisation Problems in Thermal and Fast Reactors (Germany)
H. Kuesters
NEA/NEACRP/L(1976)171The Calculation of Control Rod Worth (Germany)
H. Giese, F. Helm & G. Henneges
NEA/NEACRP/L(1976)172Reactor Physics Aspects related to LMFBR Safety (Germany)
H. Kuesters
NEA/NEACRP/L(1976)173Experimental Determination of Local Steam Bubble Velocities in BWR Fuel Elements (Germany)
D. Ceelen, P. Gebureck, D. Stegemann
NEA/NEACRP/L(1976)174Reactor Power Noise: Activities in Germany (parts a,b,c,d,e)
NEA/NEACRP/L(1976)176Specialist Meeting on inelastic scattering and fission neutron spectra Harwell
B.H. Armitage
NEA/NEACRP/L(1976)177Technical Sessions of the 19th Meeting of the Committee
Buccari, G., Fattori, G. and Mongini-Tamagnini, C., Linked Calculations - Caronte Project
NEA/NEACRP/L(1977)180Reactor Physics Activities in OECD Countries, 1977
NEA/NEACRP/L(1977)181Status of gamma Heating measurements at ANL (USA)
G.G. Simons
NEA/NEACRP/L(1977)182Potential and limitation of the heterogeneous reactor concept (USA)
W.P. Barthold, J. Beitel, E. Khan, and C. Tzanos
NEA/NEACRP/L(1977)183Summary of physics studies of a heterogeneous LMFBR core in ZPPR (USA)
NEA/NEACRP/L(1977)184Physics performance of Heterogeneous fast reactor core concept studied in
MASURCA (France)
NEA/NEACRP/L(1977)185Formulaire Carnaval IV (France)
J.P. Chaudat, A. Desprets, G. Langlet, and A. Filip
NEA/NEACRP/L(1977)186Etude d l'echauffement du aux gammas (France)
D. Calamand
NEA/NEACRP/L(1977)187A comparison of the Eigenvalue equations in k, alpha, delta, and gamma in reactor theory. Application to fast and thermal systems, in unreflected and reflected configurations (Spain)
G. Velarde, C. Ahnert, and J.M. Aragones
NEA/NEACRP/L(1977)188Etudes de "effet de vidange sodium" (France)
F. Lyon and M. Martini
NEA/NEACRP/L(1977)189Measurements of fission product effects on sodium void worth in fast reactor (Japan)
K. Koyama, H. Mitani, H. Kuroi, and J. Hirota
NEA/NEACRP/L(1977)190Incertitudes sur un pseudo-produit de fission de la filiere rapide (France)
G. Langlet, P. Coppe, and J.P. Doat
NEA/NEACRP/L(1977)191Etude de l'evolution neutronique pour la filiere a neutrons rapides au CEA: Programmes experimentaux et resultats (France)
J.P. Chaudat, G. Langlet, and L. Martin Deidier
NEA/NEACRP/L(1977)192Simulation of an HCDA sequence on the ZPPR critical facility (USA)
R.E. Kaiser, C.L. Beck, and M.J. Lineberry
NEA/NEACRP/L(1977)193On the extrapolation of ZPR sodium void measurements to the power reactor (USA)
C.L. Beck, P.J. Collins, M.J. Lineberry, and G.L. Grasseschi
NEA/NEACRP/L(1977)194Mesures de la distribution de puissance par spectrometrie gamma sur des assemblages irradies de reacteur a eau (France)
M. Darrouzet, M. Bertuol, and Santamarina
NEA/NEACRP/L(1977)195The present status of sodium void effect; predictions at GfK (Germany)
F. Helm
NEA/NEACRP/L(1977)196Measurement and calculation of 252 Cf-fission neutron induced gamma fields in iron (Germany)
S.H. Jiang, H. Werle
NEA/NEACRP/L(1977)200Proceedings of Fast Reactor Benchmark Meeting
NEA/NEACRP/L(1977)201Technical Sessions of 20th Meeting of the Committee
NEA/NEACRP/L(1978)202National Reports, 1978
NEA/NEACRP/L(1978)203Experimental Study of LMFBR Heterogeneous Core at FCA
M. Nakano et Al.
NEA/NEACRP/L(1978)204Improved Few-Group Coarse-Mesh Method for calculating Three-Dimentional Power Distribution in Fast Breeder Reactor
Y. Komano
NEA/NEACRP/L(1978)205A Static Core Performance Simulator for Light Water Reactors (SCOPERS-2) and Its Application
T. Shimooke et Al.
NEA/NEACRP/L(1978)206Application of the Finite Element Method to the Three-Dimensional Neutron Diffusion Equation
Takeharu ISE et Al.
NEA/NEACRP/L(1978)207Development of a Three Dimensional Neutron Diffusion Code Series by Leakage Iterative Method
Y. Naito
NEA/NEACRP/L(1978)208Computer Program for Control Rod Programming of BWR
NEA/NEACRP/L(1978)209Determination of Radiation Damage to Structural Components Outside the Core of PWRs
NEA/NEACRP/L(1978)210Present Status of Sodium Void Reactivity Predictions in Conventional and Nonconventional Fast Reactor Core Designs
NEA/NEACRP/L(1978)211Fast Neutron Dose in High-Temperature Gas-Cooled Reactors - Comparison of Measured and Calculated Fast Fluxes
NEA/NEACRP/L(1978)212Mesure de la Puissance Residuelle Totale Emise par les Produits de Fission Thermique de 239Pu et 233U
NEA/NEACRP/L(1978)213Formation et Disparition des Actinides Secondaires dans les Reacteurs a Eau et a Neutrons Rapides Consequences sur le Cycle du combustible
NEA/NEACRP/L(1978)214Uranium Dioxide Caramel Fuel an Alternative Fuel Cycle for Research and Test Reactors (France)
J.P. Schwartz
NEA/NEACRP/L(1978)215Present Status of the Parametric Neutronics Studies Devoted to the Optimization of Fast Breeder Power Plants (France)
J.C. Cabrillat and C. Giacometti
NEA/NEACRP/L(1978)216Present Status of the Neutronic Studies of Fast Reactor Fertile Region at CEA (France)
M. Cosimi et Al.
NEA/NEACRP/L(1978)217Interpretation of Sodium Void Measurements Performed in Pre-Racine Programme on Masurca (France)
F. Lyon et Al.
NEA/NEACRP/L(1978)218Fuel History Data Applied to Reprocessing Plant Input Inspection (France)
J. Bouchard
NEA/NEACRP/L(1978)219Experimental Control Rod Studies for Super-Phenix Performed in Masurca During the Pre-Racine Programme (France)
Y.H. Bouget
NEA/NEACRP/L(1978)220Computer Simulation and Damage Function Analysis (USA)
D.G. Doran et Al.
NEA/NEACRP/L(1978)221P.W.R. Protection System. Present Status and Improvements (France)
M. Bruyere, J.M. Lecocq
NEA/NEACRP/L(1978)222ZPPR Studies of Control Rod Interactions in Heterogeneous Cores (USA)
P.J. Collins et AL.
NEA/NEACRP/L(1978)223A Comparison between Physics Parameters in Conventional and Heterogeneous LMFBRs Using Results from ZPPR (USA)
J.P. Collins et Al.
NEA/NEACRP/L(1978)224Fast Critical Experiments with Thorium Blankets: Initial Results from ZPPR-8 (USA)
NEA/NEACRP/L(1978)225Monte Carlo - Based Validation of the ENDF/MC2-II/SDX cell Homogenization Path. (USA)
NEA/NEACRP/L(1978)226A Nodal Method for Fast Reactor Analysis (USA)
R.A. Shober
NEA/NEACRP/L(1978)227Assessment of Nuclear Data Files Via Benchmark Calculations: A Preliminary Report on the NEACRP/IAEA International Comparison Calculation of a Large LMFBR (USA)
L.G. LeSage
NEA/NEACRP/L(1978)228A Nodal-Modal Coarse Mesh method for solving the 2-group diffusion equation-
Melice (Belgium)
NEA/NEACRP/L(1978)229Summary of current NEACRP Views on fast reactor Breeding Assessment
J.Y. Barre
NEA/NEACRP/L(1978)230Technical Sessions of the 21st Meeting of the Committee (Tokyo)
6/10 November 1978
NEA/NEACRP/L(1978)231Reactor Physics Activities in OECD countries
November 1978 - September 1979
NEA/NEACRP/L(1979)232Determination of Pu accumulated in Irradiated fuels by non-destructive isotopic correlation technique
H. Tsuruta, T. Suzaki, S. Matsuura, 1979
NEA/NEACRP/L(1979)233Long term uranium demand and supply in Canada
M.F. Duret
NEA/NEACRP/L(1979)234Etudes de correlations isotopiques pour des applications aux fonctionnements des reacteurs et des usines de retraitement
M. Darrouzet, A. Giacometti
NEA/NEACRP/L(1979)235Work on gamma thermometer in CEA
A. Bonnemay et Al.
NEA/NEACRP/L(1979)236The experimental results from CRISTO qualification of the predicted criticality of fuel storages
C. Golinelli et Al.
NEA/NEACRP/L(1979)237Critically analysis for storage and shipping of nuclear fuel elements outside of reactors
G. Ermumcu et Al.
NEA/NEACRP/L(1979)238Neutronic characteristics of 1200 MWe fuelled with (Th02 - 233U)02
NEA/NEACRP/L(1979)239Preliminary study of the sub-assembly reshuffling in fast breeders
J.C. Cabrillat
NEA/NEACRP/L(1979)240KEMA: Calculations for compact storage racks for PWR fuel
W.J. Oosterkamp
NEA/NEACRP/L(1979)241An appraisal of the NEA Collaborative programme of uncertainty analysis and shielding benchmark experiments
J. Butler and H. Rief
October 1979
NEA/NEACRP/L(1979)242Technical Sessions of the 22nd Meeting of the Committee (Paris)
1st - 5th October 1979
NEA/NEACRP/L(1979)243LMFBR Intercomparison Benchmark Report
NEA/NEACRP/L(1980)244Reactor Physics Activity Reports, 1980
NEA/NEACRP/L(1980)245Fuel Pin and Subassembly Heterogeneity Effect on Neutronics Properties of a Fast Power Reactor
T. Kamei, T. Yoshida
NEA/NEACRP/L(1980)246Validation of KENO-II ANISN and Hansen-Roach Cross-Section Set on Plutonium Solution Systems
T. Matsumoto, M. Takami, R. Yumoto
NEA/NEACRP/L(1980)247Calculational Investigations on Designing Methods of Fuel Thicknesses of Annular Tanks for Plutonium Solutions
T. Matsumoto, R. Yumoto
NEA/NEACRP/L(1980)248Summary Record (Technical Sessions) of 23rd Meeting of the Committee Argonne Nat. Lab. Idaho Falls
22/26 Sept. 1980
NEA/NEACRP/L(1981)249Intercomparison of methods used to determine average parameters from resolved resonance parameters - Workshop at Data Bank.
October 1981.
NEANDC 148U (No final version of this document produced: see NEACRP-A-696 and 698)
NEA/NEACRP/L(1981)250Application of a Three-Dimensional Discrete Ordinates Transport Code to Shielding Design and Analysis.
NEA/NEACRP/L(1981)251The Danish Solution of the NRF Benchmark Problem 1980. Control Rod Ejection in a PWR.
NEA/NEACRP/L(1981)252An International Intercomparison of Results for the Reactivity Effect of Steam Ingress into the Core of a GCFR.
NEA/NEACRP/L(1981)253Decay Heat Calculations based on theoretical estimation of Average beta and gamma energies released from short lived.
NEA/NEACRP/L(1981)254Non-destructive testing of burn-ups and cooling times on PWR spent fuels.
NEA/NEACRP/L(1981)255Reactor Physics Activity Reports of Member Countries 1980-1981.
NEA/NEACRP/L(1981)256Summary Record of the 24th Meeting of NEACRP - 1981. Technical Sessions
NEA/NEACRP/L(1982)257Summary SMORN III Benchmark Test on Reactor Noise Analysis Methods -
Hirosha and Shinchara (29.3. 1982).
NEA/NEACRP/L(1982)258Reactor Physics Activities in NEA Member Countries Oct. 1981 - Sept. 1982.
NEA/NEACRP/L(1982)259Adjustment of neutron multi-group cross sections with error covariance matrices to deep penetration integral experiments.
G. Hehn et al
NEA/NEACRP/L(1982)260A study on the potential safety advantage of large heterogeneous LMFBRs.
K. Suzuki et al.
NEA/NEACRP/L(1982)262Summary Record of 25th Meeting of NEACRP 13th-17th September 1982,Karlsruhe, Germany. Technical Sessions
NEA/NEACRP/L(1982)263Proceedings of NEACRP Specialists' Meeting on Shielding Benchmark Calculation,
Paris, 1st and 2nd July 1982. - LMFBR Shielding Benchmark
G. Palmiotti and M. Salvatores
NEA/NEACRP/L(1982)264Part II of L-263 : Proceedings of NEACRP Specialists' Meeting on Shielding Benchmark Calculations, Paris, 1st and 2nd July 1982. - PWR Shielding Benchmark L-265
Reactor Physics Activities in NEA Member Countries,
October 1982 - September 1983.
G. Hehn
Reactor Physics Activities in NEA Member Countries, October 1982 to September 1983
NEA/NEACRP/L(1983)266Technical Sessions of 26th Meeting of NEACRP Committee,
Oak Ridge, USA, 17-21 October 1983.
NEA/NEACRP/L(1983)267The Yields and Spectra of Neutrons from Cascade Process in the High Energy Spallation Reaction.
K. Tsukada and Y. Nakahara.
NEA/NEACRP/L(1983)268Measurements of Tritium Production-Rate Distribution in Simulated Blanket Assemblies at the FNS.
H. Maekawa, K. Tsuda, T. Iguchi, Y. Ikeda, Y. Oyama, T. Fukumoto, T. Schi, T. Nakamura.
NEA/NEACRP/L(1983)269Validation of Neutronic Calculations for Distorted Core Configurations arising in Accident Situations of LMFBRs.
H. Kuesters.
NEA/NEACRP/L(1983)270Proceedings of the NEACRP Specialists' Meeting on the "NEACRP LMFBR Benchmark Calculation Intercomparison for Fuel Burn-Up",
Cadarache, 28-30 April 1982.
C. Palmiotti, M. Salvatores.
NEA/NEACRP/L(1983)271International Comparison Calculations for a BWR Lattice with Adjacent Gadolinium Pins.
C. Maeder, P. Wydler.
NEA/NEACRP/L(1983)272The Advanced Pressurized Water Reactor (APWE) - A Complementary System to the Closed Fuel Cycle.
B. Kuczera.
NEA/NEACRP/L(1984)273National Activity Reports, 1984.
NEA/NEACRP/L(1984)274Physics and Economic Aspects of the Recycle of LWR Uranium in LWR and Candu.
J.B. Slater, J. Griffiths.
NEA/NEACRP/L(1984)275IAEA Specialists' Meeting on Improved Utilisation of Water Reactor Fuel with Special Emphasis on Extended Burnups and Plutonium Recycling.
H. Roepenack, F. Schlemmer, G. Schlosser.
NEA/NEACRP/L(1984)276Analysis of Small-Zone Sodium-Void Experiments Performed in a Heterogeneous Fast Reactor Core.
F. Kappler, R.H. Curtis, J.M. Stevenson.
NEA/NEACRP/L(1984)277Analysis of Sodium-Void Experiments Performed in Large Heterogeneous Cores.
F. Kappler, M. Martini
NEA/NEACRP/L(1984)278Neutron Source and Spectra From ( ,n)-Reactions and Spontaneous Fission in Spent Fuel and Vitrified High Active Waste.
H.W. Wiese.
NEA/NEACRP/L(1984)279The Nodal Discrete Ordinates Method and its Application to LWR Lattice Problems.
M.R. Wagner, B. Mueller.
NEA/NEACRP/L(1984)280Testing of Evaluated Transactinium Isotope Neutron Data and Remaining Data Requirements.
H. Kuesters.
NEA/NEACRP/L(1984)281Technical Summary of NEACRP Meeting, Aix-en-Provence,
October 1984.
NEA/NEACRP/L(1984)282SMORN-IV Proceedings.
NEA/NEACRP/L(1985)284Summary Record of the Unresolved Resonance Region Meeting
Santa Fe, May 15, 1985
NEA/NEACRP/L(1985)285Reactor Physics Activities in NEA countries Sept. 84 - Sept. 85
NEA/NEACRP/L(1985)286Validation of Calculational Procedures for the Design of Light Water Tight Lattice Reactors (LWTLR) with Epithermal Spectrum
C.H.M. Broeders
NEA/NEACRP/L(1985)287New Intense Neutron Sources and Related Nuclear Data Needs
S. Cierjacks
NEA/NEACRP/L(1985)288The JRC Proposal for a European Fusion Reactor Materials Test and Development Facility
W. Kley, G.R. Bishop
NEA/NEACRP/L(1985)289Adjustment Results of Iron Cross Sections on the Basis of EURACOS and ASPIS Integral Measurements
R.D. Baechle
NEA/NEACRP/L(1985)290An FRG Proposal for an International Intercomparison of Codes for Radiation Protection Assessment of Transportation Packages
NEA/NEACRP/L(1985)291Core Physics Tests of THTR Pebble Bed Core at Zero Power
S. Brandes
NEA/NEACRP/L(1985)292Committee Summary Record (Technical Sessions) 28th NEACRP Meeting, Madrid,
2nd to 6th November 1985
NEA/NEACRP/L(1985)293Uranium recycling benchmark
C. Gollinelli
Number given to M.Cryns, waiting for final report from Cadarache
NEA/NEACRP/L(1985)294Les Tables de Probabilites; Applications au traitement des sections efficaces pour la Neutronique. Premiere partie: Dans l'hypothese statistique.
P.Ribon et J.M.Maillard
NEA/NEACRP/L(1986)295Reactor Physics Activities in NEA Member Countries 1986
NEA/NEACRP/L(1986)296Summary Record of 29th Meeting of NEACRP Committee (Technical Sessions)
Chalk River, Canada, Compiled by J.M. Stephenson
Blackcurrant cover
NEA/NEACRP/L(1986)297National Progress Reports
NEA/NEACRP/L(1986)298Highlights of the JEF Project Activities (September 1986 - September 1987)
M. Salvatores
September 1987
NEA/NEACRP/L(1986)299Standard Thermal Problem Set for the Evaluation of Heat Transfer Codes Used in the Assessment of Transport Packages.
SAND88-0380, TTC-0783, UC-71
R.E. Glass, M. Burgess, E. Livesey, J. Geoffry, S. Bourdon, D.Mennerdahl, A. Cherubini, S. Giambuzzi, P. Nagel
NEA/NEACRP/L(1987)300Final Report on the International Comparison of Calculations for the CADENZA Assemblies. The Pin-Plate Benchmark. AEE Winfrith.
M.J. Grimstone, J.L. Rowlands, J.M. Stevenson
August 1987
NEA/NEACRP/L(1987)301Summary Record of the Thirtieth NEACRP Meeting.
J.M. Stevenson
September 1987
NEA/NEACRP/L(1987)302Proceedings of a Specialists' Meeting on Data for Decay Heat
Studsvik, Sweden, 7-10 September 1987, NEANDC-U-245
September 1987
NEA/NEACRP/L(1987)303International Comparison Study of Codes Used in Decay Heat Calculations.
C. Nordborg, B. Duchemin
October 1987
NEA/NEACRP/L(1987)304Proceedings of the Symposium on Reactor Noise SMORN-V
Progress in Nuclear Energy, Pergamon Press
12th-16th October 1987 European Patent Office, Munich
T. Beynon Editor
12-16 October 1987
NEA/NEACRP/L(1988)305An Overview of SMORN-V Munich
compiled by R.C. Kryter, La Wanda E. Klobe, S.P. Hendrix, ORNL from summaries provided by Symposium Session Chairmen
OECD Paris, March 1988
NEA/NEACRP/L(1988)306Standard Problem Exercise on Criticality Codes for Dissolving Fissile Oxides in Acids. A Report of the NEACRP Criticality Working Group.
Prepared by the Oak Ridge National Laboratory (Editor: Elliot Whitesides)
issued April 90
NEA/NEACRP/L(1988)307Proceedings of the Specialists' Meeting on the Application of Critical Experiments and Operating Data to Core Design via Formal Methods of Cross Section Data Adjustment.
Host: Argonne National Laboratory. Jackson Hole Wyoming, 23-24 Sept.1988
Editor: David C. Wade
Jackson Hole, Wyoming, Sept. 23 and 24 1988
NEA/NEACRP/L(1988)308Reactor Physics Activities in NEA Member Countries
October 1987 - September 1988
NEA Committee on Reactor Physics
NEA/NEACRP/L(1988)309Summary Report on the International Comparison of NEACRP Burnup Benchmark Calculations for High Conversion Light Water Reactor Lattices.
October 1988
JAERI-M- 88-200
Hiroshi Akie, Yukio Ishiguro, Hideki Takano
NEA/NEACRP/L(1988)310Proceedings of the Seventh International Conference on Radiation Shielding
Bournemouth, 12-16 September 1988
Editors: John Butler and Atholl K. McCracken, AEE Winfrith
NEA/NEACRP/L(1988)311Investigation of Importance Weighted Infinite Multiplication Constants
in Clean and Poisoned LWHCR Lattices.
L.H.D. Berger, R. Boehme, R. Chawla, K. Gmuer
NEA/NEACRP/L(1988)312Experimental Studies of Macroscopic and Cell Heterogeneities in LWHCRs
R. Seiler, K. Gmuer, H. Hager, J.M. Paratte
NEA/NEACRP/L(1988)313Analysis of PROTEUS-LWHCR Phase-II Experiments Performed Using the AARE Modular System and JEF Based Libraries
S. Pelloni, J. Stepanek, P. VonTobel
NEA/NEACRP/L(1988)314Summary Record of 31st Meeting of the NEACRP (Technical Sessions)
O-arai, Japan, 17-21 October 1988
Compiled by F.N. McDonnell
NEA/NEACRP/L(1988)315IRMA: Interlaboratory Comparison of Fission and Capture Rate Measurement Techniques at MASURCA.
September 1988
W. Scholtyssek, M. Angelone, B. Burbidge, P. D'Hondt, K. Gmuer, G. Granget, P. Marimbeau, D. Maddison
NEA/NEACRP/L(1988)316Proceedings of a Specialist's Meeting on In-core Instrumentation and Reactor Assessment
Cadarache, 7-10 June 1988
Editor: OECD Nuclear Energy Agency
Available from OECD: 260 FF
NEA/NEACRP/L(1988)317Reactor Physics Activities in NEA Member Countries
October 1988 - September 1989
NEA Secretariat (Editor)
NEA/NEACRP/L(1989)318NEA Committee on Reactor Physics Summary Record of Thirty-second Meeting
Argonne, 9-13 October 1989
Technical Session
NEA/NEACRP/L(1989)319DECAY HEAT CALCULATION; An International Nuclear Code Comparison.
B. Duchemin, C. Nordborg. Also NEANDC-275-U.
NEA/NEACRP/L(1989)320NEACRP Theoretical Benchmark Exercise on Criticality Codes for Dissolving Fissile Oxides in Acids.
Benchmark No. 20
A. Santamarina, H. Smith, CEA Cadarache
NEA/NEACRP/L(1989)321Report on the Phase II of the International Comparison of the NEACRP Burn-up Benchmark Calculations for High Conversion Light Water Reactor Lattices
M. Takano, W. Bernnat, Y. Ishiguro, E. Sartori
NEA/NEACRP/L(1989)322Reactor Physics Activities in NEA Member Countries
October 1989 - September 1990
NEACRP Members
NEA/NEACRP/L(1990)323Status of Delayed Neutron Data, 1990
J. Blachot, M.C. Brady, A. Filip, R.W. Mills, D.R. Weaver
Published by OECD/ NEA
Also as NEANDC-299U
NEA/NEACRP/L(1990)324NEACRP Thermal Fission Product Benchmark
September 1989
M.J. Halsall, C.G. Taubman
NEA/NEACRP/L(1990)325Analysis of the Results of the OECD/NEA Fuel Dissolver Benchmark No. 19 through Neutron Balance Evaluation of International Criticality Calculations
December 1990
A. Santamarina, H. Smith (CEA)
NEA/NEACRP/L(1990)326Standard Problem Exercise on Criticality Codes for Spent LWR Fuel Transport Containers.
(Unrestricted in June 1990)
(Formerly restricted CSNI Report No. 71) May 1982
CSNI Working Group
NEA/NEACRP/L(1990)327Standard Problem Exercise on Criticality Codes for Large Arrays of Packages of Fissile Materials.
(Unrestricted in June 1990)
(Formerly Restricted CSNI Report No. 78) August 1984
CSNI Working Group
NEA/NEACRP/L(1990)328NRF Benchmark Problem 1980, Specifications and Results of Finland
November 1980
R. Kyrki, VTT
NEA/NEACRP/L(1990)329Results of Finland for NRF Benchmark Problem 1980 with Modified Gas Gap Conductivity
R. Kyrki-Rajamaki, (VTT)
NEA/NEACRP/L(1990)330Final Report on the 3-D Neutron Transport Benchmarks
T. Takeda, H. Ikeda Osaka University
NEA/NEACRP/L(1990)331NEACRP Comparison of Codes for the Radiation Protection Assessment of Transportation Packages : Solutions to Problems 1-4
A.F. Avery, H.F. Locke, AEAT Winfrith
Issued March 92
NEA/NEACRP/L(1990)332Summary Record of 33rd NEACRP Meeting (Technical Sessions)
OECD/NEA Paris, 15-19 October 1990
R. Martinelli
August 1991
R.C. Kryter, ORNL
NEA/NEACRP/L(1991)334Reactor Physics Activities in NEA Member Countries
October 1990 - September 1991
NEA Committee on Reactor Physics
NEA/NEACRP/L(1991)335NEACRP 3-D LWR Core Transient Benchmark: Specification
H. Finnemann SIEMENS/KWU, A. Galati ENEA/CRE
NEA/NEACRP/L(1991)336Benchmark Calculations of Power Distribution within Assemblies
J.C. Lefebvre (EDF/SEPTEN), J. Mondot (CEA/DRN/DER), J.P. West EDF/DPT/SPT
October 1991
NEA/NEACRP/L(1991)337Burnup-Credit Criticality Benchmark
Part 1. Simple PWR Spent Fuel Cell
(Problem Specification)
Makoto TAKANO (JAERI), (Michaele BRADY (ORNL))
NEA/NEACRP/L(1992)338NEACRP Comparison of Codes for the Radiation Protection Assessment of Transportation Packages: Solutions to Problems 5-6.
H.F. Locke, AEAT Winfrith
March 1992
NEA/NEACRP/L(1992)339Summary of the Results of the Comparison of Calculations and Measurements for the TN12 Flask Carried out under the NEACRP Intercomparison of Shielding Codes
H.F. Locke, AEAT Winfrith
March 1992
NEA/NEACRP/L(1993)340Second International Comparison on Measuring Techniques of Tritium Production Rate for Fusion Neutronics Experiments (ICMT-2)
F. Maekawa and H. Maekawa JAERI
February 1993, JAERI-M 93-017, See NEA/NSC/DOC(92)6
NEA/NEACRP/L(1993)341Not issued
NEA/NEACRP/L(1993)342Results of LWR Core Transient Benchmarks
October 1993
H. Finnemann, H, Bauer (Siemens AG), A. Galati, R. Martinelli (ENEA)
Publication stored as NSC/DOC(93)25
In preparation
NEACRP Recommendation for Standard Displacement Damage Dose Unit, September 1989, Y. Orechwa (ANL), M. Salvatores (CEA)