Screen LibraryWorkshop on Reactor Physics Calculations for Applictions in Nuclear Technology : 12 Feb.-16 Mar. 1990, International Centre for Theoretical Physics, Trieste, Italy /
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 reac...
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| Corporate Authors: | ; |
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| Group Author: | ; ; |
| Published: |
World Scientific Pub. Co.,
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| Publisher Address: | Singapore ; Teacneck, N.J. : |
| Publication Dates: | 1991. |
| Literature type: | eBook |
| Language: | English |
| Subjects: | |
| Online Access: |
www.worldscientific.com/worldscibooks/10.1142/1302#t=toc |
| Summary: |
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. |
| Carrier Form: | 1 online resource (ix,743pages) : illustrations |
| Bibliography: | Includes bibliographical references. |
| ISBN: | 9789814439398 |
| Index Number: | QC786 |
| CLC: | TL32-53 |
| Contents: | Nuclear data - Their importance and application in fission reactor physics calculations / J. J. Schmidt -- Activities of the NEA reactor physics committee and international benchmark studies for reactor physics codes / Enrico Sartori -- Activities of the OECD/NEA data bank and its computer program service / Enrico Sartori -- NJOY: A comprenhensive system for the processing of ENDF formatted nuclear data / Douglas W. Muir -- NYOY - 89: Computer exercises / Douglas W. Muir, R. MacFarlane -- Evaluated nuclear data processing and nuclear reactor calculations / Andrej Trkov -- Basic reactor physics / S. H. Levine -- Lattice cell calculations, slowing down theory and computer code WIMS; VVER type reactors / T. Kulikowska -- Preparation of input for the WIMS code / B. Sadowska -- In-core fuel management: PWR group constants generation using PSU-LEOPARD code / D. Pevec -- In-core 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 - Theory / J. R. Maiorino -- Computer code ANISN multiplying media and shielding calculation II - Code description (input/output) / J. R. Maiorino -- Computer code ANISN multiplying media and shielding calculation III - Sample problems / J. R. Maiorino -- Inverse point kinetics for the reactivity determination - Description of the KINIK code / R. Nabbi -- Fluid flow and heat transfer model of the HEATHYD code / R. Nabbi -- Reactor neutron dosimetry - Radiation damage estimates for reactor structural materials / N. P. Kocherov -- Reactor neutron dosimetry - Calculation methods in neutron spectrum unfolding / N. P. Kocherov -- Reactor neutron dosimetry - Past, present and future / N. P. Kocherov -- Advances in personal computers for scientific applications / Dermott. E. Cullen -- Review of research reactor safety documentation developed by the International Atomic Energy Agency / N. G. Chrysochoides -- List of lecturers and participants. |