MPACT verification with magnox reactor neutronics progression problems

Nicholas P. Luciano; Brian J. Ade; Kang Seog Kim; Andrew J. Conant

doi:10.1051/epjconf/202124710031

MPACT verification with magnox reactor neutronics progression problems

Nicholas P. Luciano, Brian J. Ade, Kang Seog Kim, Andrew J. Conant

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

2 Scopus citations

Abstract

MPACT is a state-of-the-art core simulator designed to perform high-fidelity analysis using whole-core, three-dimensional, pin-resolved neutron transport calculations on modern parallel computing hardware. MPACT was originally developed to model light water reactors, and its capabilities are being extended to simulate gas-cooled, graphite-moderated cores such as Magnox reactors. To verify MPACT's performance in this new application, the code is being formally benchmarked using representative problems. Progression problems are a series of example models that increase in complexity designed to test a code's performance. The progression problems include both beginning-of-cycle and depletion calculations. Reference solutions for each progression problem have been generated using Serpent 2, a continuous-energy Monte Carlo reactor physics burnup calculation code. Using the neutron multiplication eigenvalue k_eff as a metric, MPACT's performance is assessed on each of the progression problems. Initial results showed that MPACT's multigroup cross section libraries, originally developed for pressurized water reactor problems, were not sufficient to accurately solve Magnox problems. MPACT's improved performance on the progression problems is demonstrated using this new optimized cross section library.

Original language	English
Title of host publication	International Conference on Physics of Reactors
Subtitle of host publication	Transition to a Scalable Nuclear Future, PHYSOR 2020
Editors	Marat Margulis, Partrick Blaise
Publisher	EDP Sciences - Web of Conferences
Pages	2206-2213
Number of pages	8
ISBN (Electronic)	9781713827245
DOIs	https://doi.org/10.1051/epjconf/202124710031
State	Published - 2020
Event	2020 International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020 - Cambridge, United Kingdom Duration: Mar 28 2020 → Apr 2 2020

Publication series

Name	International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020
Volume	2020-March

Conference

Conference	2020 International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020
Country/Territory	United Kingdom
City	Cambridge
Period	03/28/20 → 04/2/20

Funding

This work was funded by the Office of Defense Nuclear Nonproliferation Research and Development (NA-22), within the US Department of Energy’s National Nuclear Security Administration. MPACT is a state-of-the-art core simulator developed jointly at Oak Ridge National Laboratory and the University of Michigan to perform high-fidelity analysis using whole-core, three-dimensional (3D), pin-resolved neutron transport calculations on modern parallel computing hardware. MPACT ∗Notice: This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan).

Funders	Funder number
Office of Defense Nuclear Nonproliferation Research and Development	NA-22
U.S. Department of Energy
National Nuclear Security Administration

Keywords

2D-1D
MOC
MPACT
Magnox
Serpent

Access to Document

10.1051/epjconf/202124710031

Cite this

Luciano, N. P., Ade, B. J., Kim, K. S., & Conant, A. J. (2020). MPACT verification with magnox reactor neutronics progression problems. In M. Margulis, & P. Blaise (Eds.), International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020 (pp. 2206-2213). (International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020; Vol. 2020-March). EDP Sciences - Web of Conferences. https://doi.org/10.1051/epjconf/202124710031

Luciano, Nicholas P. ; Ade, Brian J. ; Kim, Kang Seog et al. / MPACT verification with magnox reactor neutronics progression problems. International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020. editor / Marat Margulis ; Partrick Blaise. EDP Sciences - Web of Conferences, 2020. pp. 2206-2213 (International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020).

@inproceedings{46776bcffb2e446a81ac3438a5fcab46,

title = "MPACT verification with magnox reactor neutronics progression problems",

abstract = "MPACT is a state-of-the-art core simulator designed to perform high-fidelity analysis using whole-core, three-dimensional, pin-resolved neutron transport calculations on modern parallel computing hardware. MPACT was originally developed to model light water reactors, and its capabilities are being extended to simulate gas-cooled, graphite-moderated cores such as Magnox reactors. To verify MPACT's performance in this new application, the code is being formally benchmarked using representative problems. Progression problems are a series of example models that increase in complexity designed to test a code's performance. The progression problems include both beginning-of-cycle and depletion calculations. Reference solutions for each progression problem have been generated using Serpent 2, a continuous-energy Monte Carlo reactor physics burnup calculation code. Using the neutron multiplication eigenvalue keff as a metric, MPACT's performance is assessed on each of the progression problems. Initial results showed that MPACT's multigroup cross section libraries, originally developed for pressurized water reactor problems, were not sufficient to accurately solve Magnox problems. MPACT's improved performance on the progression problems is demonstrated using this new optimized cross section library.",

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author = "Luciano, {Nicholas P.} and Ade, {Brian J.} and Kim, {Kang Seog} and Conant, {Andrew J.}",

note = "Publisher Copyright: {\textcopyright} The Authors, published by EDP Sciences. This is an open access article distributed under the terms of the Creative Commons Attribution License 4.0 (http://creativecommons.org/licenses/by/4.0/).; 2020 International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020 ; Conference date: 28-03-2020 Through 02-04-2020",

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language = "English",

series = "International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020",

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Luciano, NP, Ade, BJ , Kim, KS & Conant, AJ 2020, MPACT verification with magnox reactor neutronics progression problems. in M Margulis & P Blaise (eds), International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020. International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020, vol. 2020-March, EDP Sciences - Web of Conferences, pp. 2206-2213, 2020 International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020, Cambridge, United Kingdom, 03/28/20. https://doi.org/10.1051/epjconf/202124710031

MPACT verification with magnox reactor neutronics progression problems. / Luciano, Nicholas P.; Ade, Brian J.; Kim, Kang Seog et al.
International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020. ed. / Marat Margulis; Partrick Blaise. EDP Sciences - Web of Conferences, 2020. p. 2206-2213 (International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020; Vol. 2020-March).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

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AU - Conant, Andrew J.

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N2 - MPACT is a state-of-the-art core simulator designed to perform high-fidelity analysis using whole-core, three-dimensional, pin-resolved neutron transport calculations on modern parallel computing hardware. MPACT was originally developed to model light water reactors, and its capabilities are being extended to simulate gas-cooled, graphite-moderated cores such as Magnox reactors. To verify MPACT's performance in this new application, the code is being formally benchmarked using representative problems. Progression problems are a series of example models that increase in complexity designed to test a code's performance. The progression problems include both beginning-of-cycle and depletion calculations. Reference solutions for each progression problem have been generated using Serpent 2, a continuous-energy Monte Carlo reactor physics burnup calculation code. Using the neutron multiplication eigenvalue keff as a metric, MPACT's performance is assessed on each of the progression problems. Initial results showed that MPACT's multigroup cross section libraries, originally developed for pressurized water reactor problems, were not sufficient to accurately solve Magnox problems. MPACT's improved performance on the progression problems is demonstrated using this new optimized cross section library.

AB - MPACT is a state-of-the-art core simulator designed to perform high-fidelity analysis using whole-core, three-dimensional, pin-resolved neutron transport calculations on modern parallel computing hardware. MPACT was originally developed to model light water reactors, and its capabilities are being extended to simulate gas-cooled, graphite-moderated cores such as Magnox reactors. To verify MPACT's performance in this new application, the code is being formally benchmarked using representative problems. Progression problems are a series of example models that increase in complexity designed to test a code's performance. The progression problems include both beginning-of-cycle and depletion calculations. Reference solutions for each progression problem have been generated using Serpent 2, a continuous-energy Monte Carlo reactor physics burnup calculation code. Using the neutron multiplication eigenvalue keff as a metric, MPACT's performance is assessed on each of the progression problems. Initial results showed that MPACT's multigroup cross section libraries, originally developed for pressurized water reactor problems, were not sufficient to accurately solve Magnox problems. MPACT's improved performance on the progression problems is demonstrated using this new optimized cross section library.

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M3 - Conference contribution

AN - SCOPUS:85108449334

T3 - International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020

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BT - International Conference on Physics of Reactors

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Luciano NP, Ade BJ , Kim KS , Conant AJ. MPACT verification with magnox reactor neutronics progression problems. In Margulis M, Blaise P, editors, International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020. EDP Sciences - Web of Conferences. 2020. p. 2206-2213. (International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020). doi: 10.1051/epjconf/202124710031

MPACT verification with magnox reactor neutronics progression problems

Abstract

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Keywords

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