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Title: Analysis of Differences in Void Coefficient Predictions for Mixed-Oxide-Fueled Tight-Pitch Light Water Reactor Cells

Abstract

Analysis of the benchmark problems on the void coefficient of mixed-oxide (MOX)-fueled tight-pitch cells has been performed using the Japanese SRAC code system with the JENDL-3.2 library and the French APOLLO-2 code with the CEA93 library based on JEF-2.2. The benchmark problems have been specified to investigate the physical phenomena occurring during the progressive voidage of MOX-fueled tight-pitch lattices, such as high conversion light water reactor lattices, and to evaluate the impact of nuclear data and calculational methods. Despite the most recently compiled nuclear data libraries and the sophisticated calculation schemes employed in both code systems, the k{sub {infinity}} and void reactivity values obtained by the two code systems show considerable discrepancy especially in the highly voided state. The discrepancy of k{sub {infinity}} values shows an obvious dependence on void fraction and also has been shown to be sensitive to the isotopic composition of plutonium. The observed discrepancies are analyzed by being decomposed into contributing isotopes and reactions and have been shown to be caused by a complicated balance of both negative and positive components, which are mainly attributable to differences in a limited number of isotopes including {sup 239}Pu, {sup 241}Pu, {sup 16}O, and stainless steel.

Authors:
 [1];  [1];  [1];  [2];  [2];  [3];  [4]
  1. Kyoto University (Japan)
  2. Commissariat a l'Energie Atomique (France)
  3. Musashi Institute of Technology (Japan)
  4. Osaka University (Japan)
Publication Date:
OSTI Identifier:
20804631
Resource Type:
Journal Article
Journal Name:
Nuclear Science and Engineering
Additional Journal Information:
Journal Volume: 135; Journal Issue: 1; Other Information: Copyright (c) 2006 American Nuclear Society (ANS), United States, All rights reserved. http://epubs.ans.org/; Country of input: International Atomic Energy Agency (IAEA); Journal ID: ISSN 0029-5639
Country of Publication:
United States
Language:
English
Subject:
73 NUCLEAR PHYSICS AND RADIATION PHYSICS; A CODES; BENCHMARKS; CONVERSION; ISOTOPE RATIO; MIXED OXIDE FUELS; NUCLEAR DATA COLLECTIONS; OXIDES; OXYGEN 16; PLUTONIUM; PLUTONIUM 239; PLUTONIUM 241; RADIATION TRANSPORT; REACTIVITY; STAINLESS STEELS; VOID COEFFICIENT; VOID FRACTION; VOIDS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Citation Formats

Unesaki, Hironobu, Shiroya, Seiji, Kanda, Keiji, Cathalau, Stephane, Carre, Franck-Olivier, Aizawa, Otohiko, and Takeda, Toshikazu. Analysis of Differences in Void Coefficient Predictions for Mixed-Oxide-Fueled Tight-Pitch Light Water Reactor Cells. United States: N. p., 2000. Web.
Unesaki, Hironobu, Shiroya, Seiji, Kanda, Keiji, Cathalau, Stephane, Carre, Franck-Olivier, Aizawa, Otohiko, & Takeda, Toshikazu. Analysis of Differences in Void Coefficient Predictions for Mixed-Oxide-Fueled Tight-Pitch Light Water Reactor Cells. United States.
Unesaki, Hironobu, Shiroya, Seiji, Kanda, Keiji, Cathalau, Stephane, Carre, Franck-Olivier, Aizawa, Otohiko, and Takeda, Toshikazu. Mon . "Analysis of Differences in Void Coefficient Predictions for Mixed-Oxide-Fueled Tight-Pitch Light Water Reactor Cells". United States.
@article{osti_20804631,
title = {Analysis of Differences in Void Coefficient Predictions for Mixed-Oxide-Fueled Tight-Pitch Light Water Reactor Cells},
author = {Unesaki, Hironobu and Shiroya, Seiji and Kanda, Keiji and Cathalau, Stephane and Carre, Franck-Olivier and Aizawa, Otohiko and Takeda, Toshikazu},
abstractNote = {Analysis of the benchmark problems on the void coefficient of mixed-oxide (MOX)-fueled tight-pitch cells has been performed using the Japanese SRAC code system with the JENDL-3.2 library and the French APOLLO-2 code with the CEA93 library based on JEF-2.2. The benchmark problems have been specified to investigate the physical phenomena occurring during the progressive voidage of MOX-fueled tight-pitch lattices, such as high conversion light water reactor lattices, and to evaluate the impact of nuclear data and calculational methods. Despite the most recently compiled nuclear data libraries and the sophisticated calculation schemes employed in both code systems, the k{sub {infinity}} and void reactivity values obtained by the two code systems show considerable discrepancy especially in the highly voided state. The discrepancy of k{sub {infinity}} values shows an obvious dependence on void fraction and also has been shown to be sensitive to the isotopic composition of plutonium. The observed discrepancies are analyzed by being decomposed into contributing isotopes and reactions and have been shown to be caused by a complicated balance of both negative and positive components, which are mainly attributable to differences in a limited number of isotopes including {sup 239}Pu, {sup 241}Pu, {sup 16}O, and stainless steel.},
doi = {},
journal = {Nuclear Science and Engineering},
issn = {0029-5639},
number = 1,
volume = 135,
place = {United States},
year = {2000},
month = {5}
}