NEA/NEACRP/L(1978)202 | National Reports, 1978 |
NEA/NEACRP/L(1978)203 | Experimental Study of LMFBR Heterogeneous Core at FCA<br>M. Nakano et Al. |
NEA/NEACRP/L(1978)204 | Improved Few-Group Coarse-Mesh Method for calculating Three-Dimentional Power Distribution in Fast Breeder Reactor<br>Y. Komano |
NEA/NEACRP/L(1978)205 | A Static Core Performance Simulator for Light Water Reactors (SCOPERS-2) and Its Application<br>T. Shimooke et Al. |
NEA/NEACRP/L(1978)206 | Application of the Finite Element Method to the Three-Dimensional Neutron Diffusion Equation<br>Takeharu ISE et Al. |
NEA/NEACRP/L(1978)207 | Development of a Three Dimensional Neutron Diffusion Code Series by Leakage Iterative Method<br>Y. Naito |
NEA/NEACRP/L(1978)208 | Computer Program for Control Rod Programming of BWR |
NEA/NEACRP/L(1978)209 | Determination of Radiation Damage to Structural Components Outside the Core of PWRs |
NEA/NEACRP/L(1978)210 | Present Status of Sodium Void Reactivity Predictions in Conventional and Nonconventional Fast Reactor Core Designs |
NEA/NEACRP/L(1978)211 | Fast Neutron Dose in High-Temperature Gas-Cooled Reactors - Comparison of Measured and Calculated Fast Fluxes |
NEA/NEACRP/L(1978)212 | Mesure de la Puissance Residuelle Totale Emise par les Produits de Fission Thermique de 239Pu et 233U |
NEA/NEACRP/L(1978)213 | Formation et Disparition des Actinides Secondaires dans les Reacteurs a Eau et a Neutrons Rapides Consequences sur le Cycle du combustible |
NEA/NEACRP/L(1978)214 | Uranium Dioxide Caramel Fuel an Alternative Fuel Cycle for Research and Test Reactors (France)<br>J.P. Schwartz |
NEA/NEACRP/L(1978)215 | Present 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)216 | Present Status of the Neutronic Studies of Fast Reactor Fertile Region at CEA (France)<br>M. Cosimi et Al. |
NEA/NEACRP/L(1978)217 | Interpretation of Sodium Void Measurements Performed in Pre-Racine Programme on Masurca (France)<br>F. Lyon et Al. |
NEA/NEACRP/L(1978)218 | Fuel History Data Applied to Reprocessing Plant Input Inspection (France)<br>J. Bouchard |
NEA/NEACRP/L(1978)219 | Experimental Control Rod Studies for Super-Phenix Performed in Masurca During the Pre-Racine Programme (France)<br>Y.H. Bouget |
NEA/NEACRP/L(1978)220 | Computer Simulation and Damage Function Analysis (USA)<br>D.G. Doran et Al. |
NEA/NEACRP/L(1978)221 | P.W.R. Protection System. Present Status and Improvements (France)<br>M. Bruyere, J.M. Lecocq |
NEA/NEACRP/L(1978)222 | ZPPR Studies of Control Rod Interactions in Heterogeneous Cores (USA)<br>P.J. Collins et AL. |
NEA/NEACRP/L(1978)223 | A Comparison between Physics Parameters in Conventional and Heterogeneous LMFBRs Using Results from ZPPR (USA)<br>J.P. Collins et Al. |
NEA/NEACRP/L(1978)224 | Fast Critical Experiments with Thorium Blankets: Initial Results from ZPPR-8 (USA) |
NEA/NEACRP/L(1978)225 | Monte Carlo - Based Validation of the ENDF/MC2-II/SDX cell Homogenization Path. (USA)<br>D.C. WADE |
NEA/NEACRP/L(1978)226 | A Nodal Method for Fast Reactor Analysis (USA)<br>R.A. Shober |
NEA/NEACRP/L(1978)227 | Assessment 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)228 | A Nodal-Modal Coarse Mesh method for solving the 2-group diffusion equation-<br>Melice (Belgium) |
NEA/NEACRP/L(1978)229 | Summary of current NEACRP Views on fast reactor Breeding Assessment<br>J.Y. Barre |
NEA/NEACRP/L(1978)230 | Technical Sessions of the 21st Meeting of the Committee (Tokyo)<br>6/10 November 1978 |
NEA/NEACRP/L(1978)231 | Reactor Physics Activities in OECD countries<br>November 1978 - September 1979 |
NEA/NEANDC(1978)113/U | 8th Biennial Report on the Activities of the NEANDC, S.W. Cierjacks, M.G. Sowerby, June 1978 |
NEA/NEANDC(1978)114/L | Summary of the technical sessions of the 20th Meeting of NEANDC held in Oak Ridge, USA, April 1978. |