Overview

This workshop was designed to meet the needs of those currently involved in or are planning a nuclear programme involving research and/or power fission reactors. The workshop had a broad scope including not only fission reactor core calculations, but also safety, fuel management, waste disposal reactor licensing. The lectures and computer exercises covered almost all aspects of the operation of fission reactors.This workshop introduced participants to the methods currently used in fission reactor calculations and to some computer codes in which these methods are used.Contents: Nuclear Data: Their Importance and Application in Fission Reactor Physics Calculations (J J Schmidt) Evaluated Nuclear Data Processing and Nuclear Reactor Calculations (A Trkov) Basic Reactor Physics (S H Levine) VVER Type Reactors (T Kulikowska) Preparation of Input for the WIMS Code (B Sadowska) Incore Fuel Management: PWR Group Constants Generation Using PSU-LEOPARD Code (D Pevec) Incore Fuel Management: PWR Calculations Using MCRAC (B G Petrovic) Nuclear Safety Parameters of Mixed TRIGA Cores (M Ravnik) Optimization of TRIGA Reactor Operation Using Reactor Calculations (I Mele) Computer Code ANISN Multiplying Media and Shielding Calculation I, II, III — Theory (J R Maiorino) Fluid Flow and Heat Transfer Model of the HEATHYD Code (R Nabbi) Reactor Neutron Dosimetry — Calculational Methods in Neutron Spectrum Unfolding (N P Kocherov) Advances in Personal Computers for Scientific Applications (D E Cullen) Review of Research Reactor Safety Documentation Developed by the International Atomic Energy Agency (N G Chrysochoides) and other papersReadership: Nuclear physicists.

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