Development of the multigroup cross section library for the CASL neutronics simulator MPACT: Verification
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. Depletion capability is supported by coupling SCALE-ORIGEN with MPACT. A new ENDF/B-VII.1 MPACT 51-group library has been developed by using the AMPX/SCALE and CASL-XSTools code packages based on the procedure introduced in the companion paper, “Development of the Multigroup Cross Section Library for the CASL Neutronics Simulator MPACT: Method and Procedure.” The cross section library generation procedure, cross section library, and MPACT transport capability have been verified by performing various benchmark calculations and comparing the benchmark results to the continuous-energy (CE) Monte Carlo results. Furthermore, the code-to-code comparison for the benchmarks shows that the CASL neutronics simulator MPACT and its 51-group library are working reasonably.
- Authors:
-
[1];
[1];
[1];
[2];
[3]
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Univ. of Michigan, Ann Arbor, MI (United States)
- North Carolina State Univ., Raleigh, NC (United States)
- Publication Date:
- Research Org.:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 1509584
- Alternate Identifier(s):
- OSTI ID: 1545932
- 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; VERA; MPACT; Cross section library; Benchmark; Verification
Citation Formats
Kim, Kang Seog, Gentry, Cole A., Godfrey, Andrew T., Liu, Yuxuan, and Palmtag, Scott. Development of the multigroup cross section library for the CASL neutronics simulator MPACT: Verification. United States: N. p., 2019.
Web. doi:10.1016/j.anucene.2019.03.041.
Kim, Kang Seog, Gentry, Cole A., Godfrey, Andrew T., Liu, Yuxuan, & Palmtag, Scott. Development of the multigroup cross section library for the CASL neutronics simulator MPACT: Verification. United States. https://doi.org/10.1016/j.anucene.2019.03.041
Kim, Kang Seog, Gentry, Cole A., Godfrey, Andrew T., Liu, Yuxuan, and Palmtag, Scott. Thu .
"Development of the multigroup cross section library for the CASL neutronics simulator MPACT: Verification". United States. https://doi.org/10.1016/j.anucene.2019.03.041. https://www.osti.gov/servlets/purl/1509584.
@article{osti_1509584,
title = {Development of the multigroup cross section library for the CASL neutronics simulator MPACT: Verification},
author = {Kim, Kang Seog and Gentry, Cole A. and Godfrey, Andrew T. and Liu, Yuxuan and Palmtag, Scott},
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. Depletion capability is supported by coupling SCALE-ORIGEN with MPACT. A new ENDF/B-VII.1 MPACT 51-group library has been developed by using the AMPX/SCALE and CASL-XSTools code packages based on the procedure introduced in the companion paper, “Development of the Multigroup Cross Section Library for the CASL Neutronics Simulator MPACT: Method and Procedure.” The cross section library generation procedure, cross section library, and MPACT transport capability have been verified by performing various benchmark calculations and comparing the benchmark results to the continuous-energy (CE) Monte Carlo results. Furthermore, the code-to-code comparison for the benchmarks shows that the CASL neutronics simulator MPACT and its 51-group library are working reasonably.},
doi = {10.1016/j.anucene.2019.03.041},
journal = {Annals of Nuclear Energy (Oxford)},
number = C,
volume = 132,
place = {United States},
year = {2019},
month = {4}
}
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