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

Kim, Kang Seog; Williams, Mark L.; Holcomb, Andrew M.; Wiarda, Dorothea; Jeon, Byoung Kyu; Yang, Won Sik

doi:10.1016/j.anucene.2019.04.034

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

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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:

^[1];

^[1]; Jeon, Byoung Kyu ^[2];

^[2]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Univ. of Michigan, Ann Arbor, MI (United States)

Publication Date:: Sun Apr 28 00:00:00 EDT 2019

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:: 22 GENERAL STUDIES OF NUCLEAR REACTORS; 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.

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                    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.  https://doi.org/10.1016/j.anucene.2019.04.034

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                    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.  https://doi.org/10.1016/j.anucene.2019.04.034.  https://www.osti.gov/servlets/purl/1543236.

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@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         = {Sun Apr 28 00:00:00 EDT 2019},

  month        = {Sun Apr 28 00:00:00 EDT 2019}

}

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