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Title: Monteburns and HELIOS calculated spent fuel isotopics compared to measured values

Abstract

Accurate spent-fuel isotopics are crucial for use in fuel management, mixed oxide fuel depletion calculations, reprocessing analyses, safeguards systems, and waste disposal studies. Two recently developed reactor analysis codes for calculating spent-fuel isotopics are the HELIOS code system, produced and maintained by Studsvik ScandPower, and the Monteburns code, created at Los Alamos National Laboratory. Both of these codes can be used to evaluate reactors with complex geometries and material compositions. To test the accuracy of HELIOS and Monteburns for the calculation of spent-fuel isotopics, both codes were benchmarked to measurements selected from the literature.

Authors:
;  [1];  [2]
  1. Los Alamos National Lab., NM (United States)
  2. Texas A and M Univ., College Station, TX (United States)
Publication Date:
OSTI Identifier:
678164
Report Number(s):
CONF-990605-
Journal ID: TANSAO; ISSN 0003-018X; TRN: 99:009149
Resource Type:
Journal Article
Journal Name:
Transactions of the American Nuclear Society
Additional Journal Information:
Journal Volume: 80; Conference: 1999 annual meeting of the American Nuclear Society (ANS), Boston, MA (United States), 6-10 Jun 1999; Other Information: PBD: 1999
Country of Publication:
United States
Language:
English
Subject:
99 MATHEMATICS, COMPUTERS, INFORMATION SCIENCE, MANAGEMENT, LAW, MISCELLANEOUS; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; SPENT FUELS; BURNUP; ISOTOPE RATIO; H CODES; M CODES; BENCHMARKS; PWR TYPE REACTORS; COMPARATIVE EVALUATIONS; USES

Citation Formats

Charlton, W.S., Perry, R.T., and Parish, T.A. Monteburns and HELIOS calculated spent fuel isotopics compared to measured values. United States: N. p., 1999. Web.
Charlton, W.S., Perry, R.T., & Parish, T.A. Monteburns and HELIOS calculated spent fuel isotopics compared to measured values. United States.
Charlton, W.S., Perry, R.T., and Parish, T.A. Wed . "Monteburns and HELIOS calculated spent fuel isotopics compared to measured values". United States.
@article{osti_678164,
title = {Monteburns and HELIOS calculated spent fuel isotopics compared to measured values},
author = {Charlton, W.S. and Perry, R.T. and Parish, T.A.},
abstractNote = {Accurate spent-fuel isotopics are crucial for use in fuel management, mixed oxide fuel depletion calculations, reprocessing analyses, safeguards systems, and waste disposal studies. Two recently developed reactor analysis codes for calculating spent-fuel isotopics are the HELIOS code system, produced and maintained by Studsvik ScandPower, and the Monteburns code, created at Los Alamos National Laboratory. Both of these codes can be used to evaluate reactors with complex geometries and material compositions. To test the accuracy of HELIOS and Monteburns for the calculation of spent-fuel isotopics, both codes were benchmarked to measurements selected from the literature.},
doi = {},
journal = {Transactions of the American Nuclear Society},
number = ,
volume = 80,
place = {United States},
year = {1999},
month = {9}
}