Index to unrestricted Documents for 1978

NEA/NEACRP/L(1978)202National Reports, 1978
NEA/NEACRP/L(1978)203Experimental Study of LMFBR Heterogeneous Core at FCA<br>M. Nakano et Al.
NEA/NEACRP/L(1978)204Improved Few-Group Coarse-Mesh Method for calculating Three-Dimentional Power Distribution in Fast Breeder Reactor<br>Y. Komano
NEA/NEACRP/L(1978)205A Static Core Performance Simulator for Light Water Reactors (SCOPERS-2) and Its Application<br>T. Shimooke et Al.
NEA/NEACRP/L(1978)206Application of the Finite Element Method to the Three-Dimensional Neutron Diffusion Equation<br>Takeharu ISE et Al.
NEA/NEACRP/L(1978)207Development of a Three Dimensional Neutron Diffusion Code Series by Leakage Iterative Method<br>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)<br>J.P. Schwartz
NEA/NEACRP/L(1978)215Present Status of the Parametric Neutronics Studies Devoted to the Optimization of Fast Breeder Power Plants (France)<br>J.C. Cabrillat and C. Giacometti
NEA/NEACRP/L(1978)216Present Status of the Neutronic Studies of Fast Reactor Fertile Region at CEA (France)<br>M. Cosimi et Al.
NEA/NEACRP/L(1978)217Interpretation of Sodium Void Measurements Performed in Pre-Racine Programme on Masurca (France)<br>F. Lyon et Al.
NEA/NEACRP/L(1978)218Fuel History Data Applied to Reprocessing Plant Input Inspection (France)<br>J. Bouchard
NEA/NEACRP/L(1978)219Experimental Control Rod Studies for Super-Phenix Performed in Masurca During the Pre-Racine Programme (France)<br>Y.H. Bouget
NEA/NEACRP/L(1978)220Computer Simulation and Damage Function Analysis (USA)<br>D.G. Doran et Al.
NEA/NEACRP/L(1978)221P.W.R. Protection System. Present Status and Improvements (France)<br>M. Bruyere, J.M. Lecocq
NEA/NEACRP/L(1978)222ZPPR Studies of Control Rod Interactions in Heterogeneous Cores (USA)<br>P.J. Collins et AL.
NEA/NEACRP/L(1978)223A Comparison between Physics Parameters in Conventional and Heterogeneous LMFBRs Using Results from ZPPR (USA)<br>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)<br>D.C. WADE
NEA/NEACRP/L(1978)226A Nodal Method for Fast Reactor Analysis (USA)<br>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)<br>L.G. LeSage
NEA/NEACRP/L(1978)228A Nodal-Modal Coarse Mesh method for solving the 2-group diffusion equation-<br>Melice (Belgium)
NEA/NEACRP/L(1978)229Summary of current NEACRP Views on fast reactor Breeding Assessment<br>J.Y. Barre
NEA/NEACRP/L(1978)230Technical Sessions of the 21st Meeting of the Committee (Tokyo)<br>6/10 November 1978
NEA/NEACRP/L(1978)231Reactor Physics Activities in OECD countries<br>November 1978 - September 1979
NEA/NEANDC(1978)113/U8th Biennial Report on the Activities of the NEANDC, S.W. Cierjacks, M.G. Sowerby, June 1978
NEA/NEANDC(1978)114/LSummary of the technical sessions of the 20th Meeting of NEANDC held in Oak Ridge, USA, April 1978.