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Title: Development of the multigroup cross section library for the CASL neutronics simulator MPACT: Method and procedure

Abstract

The MPACT neutronics module of the Consortium for Advanced Simulation of Light Water Reactors (CASL) core simulator is a 3D whole core transport code being developed for the CASL toolset known as the Virtual Environment for Reactor Analysis (VERA). Key characteristics of the MPACT code include a subgroup method for resonance self-shielding and a whole-core transport solver with a 2D/1D synthesis method. The AMPX and SCALE code packages have been significantly improved to include intermediate resonance parameters, as well as new modules to enhance the accuracy of resonance data and scattering matrices for the Bondarenko approach and transport cross sections of hydrogen. In addition, CASL XSTools have been developed to generate the MPACT multigroup cross section library. A simple super-homogenization method for 238U has been developed to resolve reaction rate discrepancy issues caused by angle-dependent total cross sections, poor scattering matrices, and a poor resonance interference model at coarse group structure. Here, due to the limitation of computing capacity that can occur even in high performance computing, a new 51-group structure has been developed for efficient simulation that is applicable for both pressurized water reactor (PWR) and boiling water reactor (BWR) simulations. A new ENDF/B-VII.1 MPACT 51-group library has beenmore » developed using the AMPX/SCALE and XSTools code packages, and it has been verified and validated by performing various benchmark calculations.« less

Authors:
ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1543238
Alternate Identifier(s):
OSTI ID: 1547218
Grant/Contract Number:  
AC05-00OR22725
Resource Type:
Journal Article: Accepted Manuscript
Journal Name:
Annals of Nuclear Energy (Oxford)
Additional Journal Information:
Journal Volume: 133; Journal Issue: C; Journal ID: ISSN 0306-4549
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
Multigroup cross section; AMPX/SCALE; Resonance self-shielding; SPH; MPACT

Citation Formats

Kim, Kang Seog, Williams, Mark L., Wiarda, Dorothea, and Clarno, Kevin T. Development of the multigroup cross section library for the CASL neutronics simulator MPACT: Method and procedure. United States: N. p., 2019. Web. doi:10.1016/j.anucene.2019.05.010.
Kim, Kang Seog, Williams, Mark L., Wiarda, Dorothea, & Clarno, Kevin T. Development of the multigroup cross section library for the CASL neutronics simulator MPACT: Method and procedure. United States. doi:10.1016/j.anucene.2019.05.010.
Kim, Kang Seog, Williams, Mark L., Wiarda, Dorothea, and Clarno, Kevin T. Mon . "Development of the multigroup cross section library for the CASL neutronics simulator MPACT: Method and procedure". United States. doi:10.1016/j.anucene.2019.05.010.
@article{osti_1543238,
title = {Development of the multigroup cross section library for the CASL neutronics simulator MPACT: Method and procedure},
author = {Kim, Kang Seog and Williams, Mark L. and Wiarda, Dorothea and Clarno, Kevin T.},
abstractNote = {The MPACT neutronics module of the Consortium for Advanced Simulation of Light Water Reactors (CASL) core simulator is a 3D whole core transport code being developed for the CASL toolset known as the Virtual Environment for Reactor Analysis (VERA). Key characteristics of the MPACT code include a subgroup method for resonance self-shielding and a whole-core transport solver with a 2D/1D synthesis method. The AMPX and SCALE code packages have been significantly improved to include intermediate resonance parameters, as well as new modules to enhance the accuracy of resonance data and scattering matrices for the Bondarenko approach and transport cross sections of hydrogen. In addition, CASL XSTools have been developed to generate the MPACT multigroup cross section library. A simple super-homogenization method for 238U has been developed to resolve reaction rate discrepancy issues caused by angle-dependent total cross sections, poor scattering matrices, and a poor resonance interference model at coarse group structure. Here, due to the limitation of computing capacity that can occur even in high performance computing, a new 51-group structure has been developed for efficient simulation that is applicable for both pressurized water reactor (PWR) and boiling water reactor (BWR) simulations. A new ENDF/B-VII.1 MPACT 51-group library has been developed using the AMPX/SCALE and XSTools code packages, and it has been verified and validated by performing various benchmark calculations.},
doi = {10.1016/j.anucene.2019.05.010},
journal = {Annals of Nuclear Energy (Oxford)},
issn = {0306-4549},
number = C,
volume = 133,
place = {United States},
year = {2019},
month = {5}
}

Journal Article:
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