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Title: Comparisons of Cell Calculations for Uranium-Free Light Water Reactor Fuels

Abstract

An effective way to reduce the large quantities of Pu currently accumulated worldwide would be to use uranium-free fuel in light water reactors (LWRs) so that no new Pu is produced. Such a possibility could be provided by an LWR fuel consisting of Pu in a neutronically inert matrix. It may be necessary to add a burnable absorber or thorium to reduce the reactivity swing during burnup. The methods and data currently used for LWR analyses have not been tested in conjunction with such exotic fuel materials. An international exercise has accordingly been launched to compare the relative performance of different code systems and the accuracy of the basic data. Comparison of the results of cell calculations done with fixed isotopic densities against reference Monte Carlo results shows fairly small but systematic differences in the multiplication factors. A sensitivity analysis done with different basic cross section libraries and the same code system allows one to distinguish between the effects of the codes and those of the databases.The results of the burnup calculations indicate a fair agreement in k{sub {infinity}} both at beginning of life (BOL) and after 1200 days of irradiation [end of life (EOL)] under conditions representative of amore » present-day pressurized water reactor. At BOL, the fuel temperature coefficients agree fairly well among the different contributions, but unacceptably large differences are observed at EOL. The void coefficients agree well for low voidage, but for void fractions >90%, there are significant effects mostly due to the databases used. The agreement in the calculated boron worths is good.« less

Authors:
 [1];  [2];  [1];  [3]; ;  [4];  [4];  [1];  [3];  [2]
  1. Paul Scherrer Institute (Switzerland)
  2. Japan Atomic Energy Research Institute (Japan)
  3. Commissariat a l'Energie Atomique (France)
  4. Polytechnic of Milan (Italy)
Publication Date:
OSTI Identifier:
20822159
Resource Type:
Journal Article
Journal Name:
Nuclear Technology
Additional Journal Information:
Journal Volume: 130; Journal Issue: 2; 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 0029-5450
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BORON; BURNUP; COMPARATIVE EVALUATIONS; DENSITY; MONTE CARLO METHOD; MULTIPLICATION FACTORS; NUCLEAR FUELS; PERFORMANCE; PWR TYPE REACTORS; REACTIVITY; SENSITIVITY ANALYSIS; TEMPERATURE COEFFICIENT; THORIUM; VOID COEFFICIENT; VOID FRACTION

Citation Formats

Paratte, Jean-M., Akie, Hiroshi, Chawla, Rakesh, Delpech, Marc, Kloosterman, Jan Leen, Lombardi, Carlo, Mazzola, Alessandro, Pelloni, Sandro, Peneliau, Yannick, and Takano, Hideki. Comparisons of Cell Calculations for Uranium-Free Light Water Reactor Fuels. United States: N. p., 2000. Web.
Paratte, Jean-M., Akie, Hiroshi, Chawla, Rakesh, Delpech, Marc, Kloosterman, Jan Leen, Lombardi, Carlo, Mazzola, Alessandro, Pelloni, Sandro, Peneliau, Yannick, & Takano, Hideki. Comparisons of Cell Calculations for Uranium-Free Light Water Reactor Fuels. United States.
Paratte, Jean-M., Akie, Hiroshi, Chawla, Rakesh, Delpech, Marc, Kloosterman, Jan Leen, Lombardi, Carlo, Mazzola, Alessandro, Pelloni, Sandro, Peneliau, Yannick, and Takano, Hideki. Mon . "Comparisons of Cell Calculations for Uranium-Free Light Water Reactor Fuels". United States.
@article{osti_20822159,
title = {Comparisons of Cell Calculations for Uranium-Free Light Water Reactor Fuels},
author = {Paratte, Jean-M. and Akie, Hiroshi and Chawla, Rakesh and Delpech, Marc and Kloosterman, Jan Leen and Lombardi, Carlo and Mazzola, Alessandro and Pelloni, Sandro and Peneliau, Yannick and Takano, Hideki},
abstractNote = {An effective way to reduce the large quantities of Pu currently accumulated worldwide would be to use uranium-free fuel in light water reactors (LWRs) so that no new Pu is produced. Such a possibility could be provided by an LWR fuel consisting of Pu in a neutronically inert matrix. It may be necessary to add a burnable absorber or thorium to reduce the reactivity swing during burnup. The methods and data currently used for LWR analyses have not been tested in conjunction with such exotic fuel materials. An international exercise has accordingly been launched to compare the relative performance of different code systems and the accuracy of the basic data. Comparison of the results of cell calculations done with fixed isotopic densities against reference Monte Carlo results shows fairly small but systematic differences in the multiplication factors. A sensitivity analysis done with different basic cross section libraries and the same code system allows one to distinguish between the effects of the codes and those of the databases.The results of the burnup calculations indicate a fair agreement in k{sub {infinity}} both at beginning of life (BOL) and after 1200 days of irradiation [end of life (EOL)] under conditions representative of a present-day pressurized water reactor. At BOL, the fuel temperature coefficients agree fairly well among the different contributions, but unacceptably large differences are observed at EOL. The void coefficients agree well for low voidage, but for void fractions >90%, there are significant effects mostly due to the databases used. The agreement in the calculated boron worths is good.},
doi = {},
journal = {Nuclear Technology},
issn = {0029-5450},
number = 2,
volume = 130,
place = {United States},
year = {2000},
month = {5}
}