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Title: The SCALE/AMPX multigroup cross section processing for fast reactor analysis

Abstract

The SCALE/AMPX multigroup (MG) cross section processing procedure has been updated to minimize reactivity differences for fast reactor designs and boiling water reactors (BWRs) with very high void fractions to provide excellent agreement with continuous-energy reference calculations. SCALE MG calculations are widely applied to thermal spectrum light-water reactor (LWR) systems as well as fast spectrum metallic systems of interest to National Nuclear Security Administration. With growing interest from industry and regulators in applying SCALE for the design of fast spectrum reactors, both sodium and molten salt, and in the licensing of power up rates for BWRs, it is desirable to review the SCALE/AMPX procedure for unresolved resonance self-shielded data and high energy neutron spectra. The data were improved by generating MG unresolved resonance data based on the analytic probability table method with the narrow resonance approximation as well as the use of a very fine group structure typically used in fast system analysis. This study focused on verifying the probability table and the SCALE/AMPX MG cross section processing procedure by performing reaction rate analysis and benchmark calculations for various fast reactor and high void BWR systems. Here, results indicate that the improved SCALE/AMPX MG cross section processing provides excellent resultsmore » for the fast reactor analysis.« less

Authors:
ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1];  [2]; ORCiD logo [2]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  2. Univ. of Michigan, Ann Arbor, MI (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1543236
Grant/Contract Number:  
AC05-00OR22725
Resource Type:
Accepted Manuscript
Journal Name:
Annals of Nuclear Energy (Oxford)
Additional Journal Information:
Journal Name: Annals of Nuclear Energy (Oxford); Journal Volume: 132; Journal Issue: C; Journal ID: ISSN 0306-4549
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
SCALE/AMPX; Unresolved probability table; Cross section; Fast reactor

Citation Formats

Kim, Kang Seog, Williams, Mark L., Holcomb, Andrew M., Wiarda, Dorothea, Jeon, Byoung Kyu, and Yang, Won Sik. The SCALE/AMPX multigroup cross section processing for fast reactor analysis. United States: N. p., 2019. Web. doi:10.1016/j.anucene.2019.04.034.
Kim, Kang Seog, Williams, Mark L., Holcomb, Andrew M., Wiarda, Dorothea, Jeon, Byoung Kyu, & Yang, Won Sik. The SCALE/AMPX multigroup cross section processing for fast reactor analysis. United States. doi:10.1016/j.anucene.2019.04.034.
Kim, Kang Seog, Williams, Mark L., Holcomb, Andrew M., Wiarda, Dorothea, Jeon, Byoung Kyu, and Yang, Won Sik. Sun . "The SCALE/AMPX multigroup cross section processing for fast reactor analysis". United States. doi:10.1016/j.anucene.2019.04.034.
@article{osti_1543236,
title = {The SCALE/AMPX multigroup cross section processing for fast reactor analysis},
author = {Kim, Kang Seog and Williams, Mark L. and Holcomb, Andrew M. and Wiarda, Dorothea and Jeon, Byoung Kyu and Yang, Won Sik},
abstractNote = {The SCALE/AMPX multigroup (MG) cross section processing procedure has been updated to minimize reactivity differences for fast reactor designs and boiling water reactors (BWRs) with very high void fractions to provide excellent agreement with continuous-energy reference calculations. SCALE MG calculations are widely applied to thermal spectrum light-water reactor (LWR) systems as well as fast spectrum metallic systems of interest to National Nuclear Security Administration. With growing interest from industry and regulators in applying SCALE for the design of fast spectrum reactors, both sodium and molten salt, and in the licensing of power up rates for BWRs, it is desirable to review the SCALE/AMPX procedure for unresolved resonance self-shielded data and high energy neutron spectra. The data were improved by generating MG unresolved resonance data based on the analytic probability table method with the narrow resonance approximation as well as the use of a very fine group structure typically used in fast system analysis. This study focused on verifying the probability table and the SCALE/AMPX MG cross section processing procedure by performing reaction rate analysis and benchmark calculations for various fast reactor and high void BWR systems. Here, results indicate that the improved SCALE/AMPX MG cross section processing provides excellent results for the fast reactor analysis.},
doi = {10.1016/j.anucene.2019.04.034},
journal = {Annals of Nuclear Energy (Oxford)},
number = C,
volume = 132,
place = {United States},
year = {2019},
month = {4}
}

Journal Article:
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This content will become publicly available on April 28, 2020
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