IMPROVEMENT OF THE SCALE-XSPROC CAPABILITY FOR HIGH-TEMPERATURE GAS-COOLED REACTOR ANALYSIS

Kang Seog Kim; Andrew M. Holcomb; Friederike Bostelmann; Dorothea Wiarda; Brandon R. Langley; William A. Wieselquist

doi:10.13182/M&C21-33898

IMPROVEMENT OF THE SCALE-XSPROC CAPABILITY FOR HIGH-TEMPERATURE GAS-COOLED REACTOR ANALYSIS

Kang Seog Kim, Andrew M. Holcomb, Friederike Bostelmann, Dorothea Wiarda, Brandon R. Langley, William A. Wieselquist

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

2 Scopus citations

Abstract

The SCALE-XSProc multigroup (MG) cross section processing procedure, which is based on the CENTRM pointwise (PW) slowing-down calculation, is the primary procedure for processing problem-dependent self-shielded MG cross sections and scattering matrices for neutron transport calculations. Recently, significant reactivity bias and reaction rate differences were observed compared with continuous energy Monte Carlo calculations for various prismatic and pebble-type fuels with tristructural isotropic particles in high-temperature gas-cooled reactors. Error sources for these issues were determined, and five areas for improvement were identified and addressed in the SCALE-XSProc MG cross section processing: (1) 10 eV thermal cutoff energy for the free gas model, (2) on-the-fly adjustments to the thermal scattering matrix, (3) normalization of PW neutron flux, (4) improvement of self-shielded cross sections at the epithermal energy range, and (5) improvement of double heterogeneity capabilities.

Original language	English
Title of host publication	Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021
Publisher	American Nuclear Society
Pages	2342-2349
Number of pages	8
ISBN (Electronic)	9781713886310
DOIs	https://doi.org/10.13182/M&C21-33898
State	Published - 2021
Event	2021 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021 - Virtual, Online Duration: Oct 3 2021 → Oct 7 2021

Publication series

Name	Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021

Conference

Conference	2021 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021
City	Virtual, Online
Period	10/3/21 → 10/7/21

Funding

This research was supported by the US Nuclear Regulatory Commission Office of Research. 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). This research was supported by the US Nuclear Regulatory Commission Office of Research.  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
DOE Public Access Plan
U.S. Department of Energy
U.S. Nuclear Regulatory Commission

Keywords

XSProc
double heterogeneity
high-temperature gas-cooled reactors

Access to Document

10.13182/M&C21-33898

Cite this

Kim, K. S., Holcomb, A. M., Bostelmann, F., Wiarda, D., Langley, B. R., & Wieselquist, W. A. (2021). IMPROVEMENT OF THE SCALE-XSPROC CAPABILITY FOR HIGH-TEMPERATURE GAS-COOLED REACTOR ANALYSIS. In Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021 (pp. 2342-2349). (Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021). American Nuclear Society. https://doi.org/10.13182/M&C21-33898

Kim, Kang Seog ; Holcomb, Andrew M. ; Bostelmann, Friederike et al. / IMPROVEMENT OF THE SCALE-XSPROC CAPABILITY FOR HIGH-TEMPERATURE GAS-COOLED REACTOR ANALYSIS. Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021. American Nuclear Society, 2021. pp. 2342-2349 (Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021).

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title = "IMPROVEMENT OF THE SCALE-XSPROC CAPABILITY FOR HIGH-TEMPERATURE GAS-COOLED REACTOR ANALYSIS",

abstract = "The SCALE-XSProc multigroup (MG) cross section processing procedure, which is based on the CENTRM pointwise (PW) slowing-down calculation, is the primary procedure for processing problem-dependent self-shielded MG cross sections and scattering matrices for neutron transport calculations. Recently, significant reactivity bias and reaction rate differences were observed compared with continuous energy Monte Carlo calculations for various prismatic and pebble-type fuels with tristructural isotropic particles in high-temperature gas-cooled reactors. Error sources for these issues were determined, and five areas for improvement were identified and addressed in the SCALE-XSProc MG cross section processing: (1) 10 eV thermal cutoff energy for the free gas model, (2) on-the-fly adjustments to the thermal scattering matrix, (3) normalization of PW neutron flux, (4) improvement of self-shielded cross sections at the epithermal energy range, and (5) improvement of double heterogeneity capabilities.",

keywords = "XSProc, double heterogeneity, high-temperature gas-cooled reactors",

author = "Kim, {Kang Seog} and Holcomb, {Andrew M.} and Friederike Bostelmann and Dorothea Wiarda and Langley, {Brandon R.} and Wieselquist, {William A.}",

note = "Publisher Copyright: Copyright {\textcopyright} 2021 AMERICAN NUCLEAR SOCIETY, INCORPORATED, LA GRANGE PARK, ILLINOIS 60526.All rights reserved.; 2021 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021 ; Conference date: 03-10-2021 Through 07-10-2021",

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doi = "10.13182/M&C21-33898",

language = "English",

series = "Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021",

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Kim, KS , Holcomb, AM , Bostelmann, F , Wiarda, D , Langley, BR & Wieselquist, WA 2021, IMPROVEMENT OF THE SCALE-XSPROC CAPABILITY FOR HIGH-TEMPERATURE GAS-COOLED REACTOR ANALYSIS. in Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021. Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021, American Nuclear Society, pp. 2342-2349, 2021 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021, Virtual, Online, 10/3/21. https://doi.org/10.13182/M&C21-33898

IMPROVEMENT OF THE SCALE-XSPROC CAPABILITY FOR HIGH-TEMPERATURE GAS-COOLED REACTOR ANALYSIS. / Kim, Kang Seog ; Holcomb, Andrew M.; Bostelmann, Friederike et al.
Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021. American Nuclear Society, 2021. p. 2342-2349 (Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021).

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

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AU - Kim, Kang Seog

AU - Holcomb, Andrew M.

AU - Bostelmann, Friederike

AU - Wiarda, Dorothea

AU - Langley, Brandon R.

AU - Wieselquist, William A.

PY - 2021

Y1 - 2021

N2 - The SCALE-XSProc multigroup (MG) cross section processing procedure, which is based on the CENTRM pointwise (PW) slowing-down calculation, is the primary procedure for processing problem-dependent self-shielded MG cross sections and scattering matrices for neutron transport calculations. Recently, significant reactivity bias and reaction rate differences were observed compared with continuous energy Monte Carlo calculations for various prismatic and pebble-type fuels with tristructural isotropic particles in high-temperature gas-cooled reactors. Error sources for these issues were determined, and five areas for improvement were identified and addressed in the SCALE-XSProc MG cross section processing: (1) 10 eV thermal cutoff energy for the free gas model, (2) on-the-fly adjustments to the thermal scattering matrix, (3) normalization of PW neutron flux, (4) improvement of self-shielded cross sections at the epithermal energy range, and (5) improvement of double heterogeneity capabilities.

AB - The SCALE-XSProc multigroup (MG) cross section processing procedure, which is based on the CENTRM pointwise (PW) slowing-down calculation, is the primary procedure for processing problem-dependent self-shielded MG cross sections and scattering matrices for neutron transport calculations. Recently, significant reactivity bias and reaction rate differences were observed compared with continuous energy Monte Carlo calculations for various prismatic and pebble-type fuels with tristructural isotropic particles in high-temperature gas-cooled reactors. Error sources for these issues were determined, and five areas for improvement were identified and addressed in the SCALE-XSProc MG cross section processing: (1) 10 eV thermal cutoff energy for the free gas model, (2) on-the-fly adjustments to the thermal scattering matrix, (3) normalization of PW neutron flux, (4) improvement of self-shielded cross sections at the epithermal energy range, and (5) improvement of double heterogeneity capabilities.

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BT - Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021

PB - American Nuclear Society

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Y2 - 3 October 2021 through 7 October 2021

ER -

Kim KS , Holcomb AM , Bostelmann F , Wiarda D , Langley BR , Wieselquist WA. IMPROVEMENT OF THE SCALE-XSPROC CAPABILITY FOR HIGH-TEMPERATURE GAS-COOLED REACTOR ANALYSIS. In Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021. American Nuclear Society. 2021. p. 2342-2349. (Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021). doi: 10.13182/M&C21-33898

IMPROVEMENT OF THE SCALE-XSPROC CAPABILITY FOR HIGH-TEMPERATURE GAS-COOLED REACTOR ANALYSIS

Abstract

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Keywords

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