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Title: A lumped parameter method of characteristics approach and multigroup kernels applied to the subgroup self-shielding calculation in MPACT

Abstract

An essential component of the neutron transport solver is the resonance self-shielding calculation used to determine equivalence cross sections. The neutron transport code, MPACT, is currently using the subgroup self-shielding method, in which the method of characteristics (MOC) is used to solve purely absorbing fixed-source problems. Recent efforts incorporating multigroup kernels to the MOC solvers in MPACT have reduced runtime by roughly 2×. Applying the same concepts for self-shielding and developing a novel lumped parameter approach to MOC, substantial improvements have also been made to the self-shielding computational efficiency without sacrificing any accuracy. These new multigroup and lumped parameter capabilities have been demonstrated on two test cases: (1) a single lattice with quarter symmetry known as VERA (Virtual Environment for Reactor Applications) Progression Problem 2a and (2) a two-dimensional quarter-core slice known as Problem 5a-2D. From these cases, self-shielding computational time was reduced by roughly 3–4×, with a corresponding 15–20% increase in overall memory burden. An azimuthal angle sensitivity study also shows that only half as many angles are needed, yielding an additional speedup of 2×. In total, the improvements yield roughly a 7–8× speedup. Furthermore given these performance benefits, these approaches have been adopted as the default in MPACT.

Authors:
ORCiD logo; ; ;
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility (OLCF)
Sponsoring Org.:
USDOE Office of Science (SC)
OSTI Identifier:
1373334
Alternate Identifier(s):
OSTI ID: 1407807
Grant/Contract Number:  
AC05-00OR22725
Resource Type:
Published Article
Journal Name:
Nuclear Engineering and Technology
Additional Journal Information:
Journal Name: Nuclear Engineering and Technology Journal Volume: 49 Journal Issue: 6; Journal ID: ISSN 1738-5733
Publisher:
Elsevier
Country of Publication:
Korea, Republic of
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; CASL; Lumped Parameter; M&C 2017; MOC; MPACT; Subgroup Self-Shielding

Citation Formats

Stimpson, Shane, Liu, Yuxuan, Collins, Benjamin, and Clarno, Kevin. A lumped parameter method of characteristics approach and multigroup kernels applied to the subgroup self-shielding calculation in MPACT. Korea, Republic of: N. p., 2017. Web. doi:10.1016/j.net.2017.07.006.
Stimpson, Shane, Liu, Yuxuan, Collins, Benjamin, & Clarno, Kevin. A lumped parameter method of characteristics approach and multigroup kernels applied to the subgroup self-shielding calculation in MPACT. Korea, Republic of. doi:10.1016/j.net.2017.07.006.
Stimpson, Shane, Liu, Yuxuan, Collins, Benjamin, and Clarno, Kevin. Fri . "A lumped parameter method of characteristics approach and multigroup kernels applied to the subgroup self-shielding calculation in MPACT". Korea, Republic of. doi:10.1016/j.net.2017.07.006.
@article{osti_1373334,
title = {A lumped parameter method of characteristics approach and multigroup kernels applied to the subgroup self-shielding calculation in MPACT},
author = {Stimpson, Shane and Liu, Yuxuan and Collins, Benjamin and Clarno, Kevin},
abstractNote = {An essential component of the neutron transport solver is the resonance self-shielding calculation used to determine equivalence cross sections. The neutron transport code, MPACT, is currently using the subgroup self-shielding method, in which the method of characteristics (MOC) is used to solve purely absorbing fixed-source problems. Recent efforts incorporating multigroup kernels to the MOC solvers in MPACT have reduced runtime by roughly 2×. Applying the same concepts for self-shielding and developing a novel lumped parameter approach to MOC, substantial improvements have also been made to the self-shielding computational efficiency without sacrificing any accuracy. These new multigroup and lumped parameter capabilities have been demonstrated on two test cases: (1) a single lattice with quarter symmetry known as VERA (Virtual Environment for Reactor Applications) Progression Problem 2a and (2) a two-dimensional quarter-core slice known as Problem 5a-2D. From these cases, self-shielding computational time was reduced by roughly 3–4×, with a corresponding 15–20% increase in overall memory burden. An azimuthal angle sensitivity study also shows that only half as many angles are needed, yielding an additional speedup of 2×. In total, the improvements yield roughly a 7–8× speedup. Furthermore given these performance benefits, these approaches have been adopted as the default in MPACT.},
doi = {10.1016/j.net.2017.07.006},
journal = {Nuclear Engineering and Technology},
number = 6,
volume = 49,
place = {Korea, Republic of},
year = {2017},
month = {9}
}

Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record
DOI: 10.1016/j.net.2017.07.006

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