Development of the multigroup cross section library for the CASL neutronics simulator MPACT: Verification

Kang Seog Kim; Cole A. Gentry; Andrew T. Godfrey; Yuxuan Liu; Scott Palmtag

doi:10.1016/j.anucene.2019.03.041

Development of the multigroup cross section library for the CASL neutronics simulator MPACT: Verification

Kang Seog Kim, Cole A. Gentry, Andrew T. Godfrey, Yuxuan Liu, Scott Palmtag

Research and Test Reactor Physics

Research output: Contribution to journal › Article › peer-review

20 Scopus citations

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. The code-to-code comparison for the benchmarks shows that the CASL neutronics simulator MPACT and its 51-group library are working reasonably.

Original language	English
Pages (from-to)	1-23
Number of pages	23
Journal	Annals of Nuclear Energy
Volume	132
DOIs	https://doi.org/10.1016/j.anucene.2019.03.041
State	Published - Oct 2019

Funding

This research was supported by the Consortium for Advanced Simulation of Light Water Reactors (http://www.casl.gov), an Energy Innovation Hub (http://www.energy.gov/hubs) for Modeling and Simulation of Nuclear Reactors under U.S. Department of Energy Contract No. DE-AC05-00OR22725 . This research was supported by the Consortium for Advanced Simulation of Light Water Reactors (http://www.casl.gov), an Energy Innovation Hub (http://www.energy.gov/hubs) for Modeling and Simulation of Nuclear Reactors under U.S. Department of Energy Contract No. DE-AC05-00OR22725.

Funders	Funder number
Consortium for Advanced Simulation of Light Water Reactors
Energy Innovation Hub
Modeling and Simulation of Nuclear Reactors
U.S. Department of Energy	DE-AC05-00OR22725

Keywords

Benchmark
Cross section library
MPACT
VERA
Verification

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10.1016/j.anucene.2019.03.041

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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. The code-to-code comparison for the benchmarks shows that the CASL neutronics simulator MPACT and its 51-group library are working reasonably.",

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Development of the multigroup cross section library for the CASL neutronics simulator MPACT: Verification

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