NEA/NEACRP/L(1978)202	National Reports, 1978
NEA/NEACRP/L(1978)203	Experimental Study of LMFBR Heterogeneous Core at FCA 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 Y. Komano
NEA/NEACRP/L(1978)205	A Static Core Performance Simulator for Light Water Reactors (SCOPERS-2) and Its Application T. Shimooke et Al.
NEA/NEACRP/L(1978)206	Application of the Finite Element Method to the Three-Dimensional Neutron Diffusion Equation Takeharu ISE et Al.
NEA/NEACRP/L(1978)207	Development of a Three Dimensional Neutron Diffusion Code Series by Leakage Iterative Method 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) 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) 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) M. Cosimi et Al.
NEA/NEACRP/L(1978)217	Interpretation of Sodium Void Measurements Performed in Pre-Racine Programme on Masurca (France) F. Lyon et Al.
NEA/NEACRP/L(1978)218	Fuel History Data Applied to Reprocessing Plant Input Inspection (France) J. Bouchard
NEA/NEACRP/L(1978)219	Experimental Control Rod Studies for Super-Phenix Performed in Masurca During the Pre-Racine Programme (France) Y.H. Bouget
NEA/NEACRP/L(1978)220	Computer Simulation and Damage Function Analysis (USA) D.G. Doran et Al.
NEA/NEACRP/L(1978)221	P.W.R. Protection System. Present Status and Improvements (France) M. Bruyere, J.M. Lecocq
NEA/NEACRP/L(1978)222	ZPPR Studies of Control Rod Interactions in Heterogeneous Cores (USA) 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) 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) D.C. WADE
NEA/NEACRP/L(1978)226	A Nodal Method for Fast Reactor Analysis (USA) 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) L.G. LeSage
NEA/NEACRP/L(1978)228	A Nodal-Modal Coarse Mesh method for solving the 2-group diffusion equation- Melice (Belgium)
NEA/NEACRP/L(1978)229	Summary of current NEACRP Views on fast reactor Breeding Assessment J.Y. Barre
NEA/NEACRP/L(1978)230	Technical Sessions of the 21st Meeting of the Committee (Tokyo) 6/10 November 1978
NEA/NEACRP/L(1978)231	Reactor Physics Activities in OECD countries November 1978 - September 1979