SPATIALLY DEPENDENT RESONANCE SELF-SHIELDING CAPABILITY FOR NON-UNIFORM TEMPERATURE PROFILE IN SCALE-6.3 XSPROC-BONAMI

Kang Seog Kim; Andrew M. Holcomb; William A. Wieselquist

doi:10.13182/M&C21-33765

SPATIALLY DEPENDENT RESONANCE SELF-SHIELDING CAPABILITY FOR NON-UNIFORM TEMPERATURE PROFILE IN SCALE-6.3 XSPROC-BONAMI

Kang Seog Kim, Andrew M. Holcomb, William A. Wieselquist

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

2 Scopus citations

Abstract

For some fuel depletion and performance simulations, temperature-dependent rings of fuel are preferred. This has typically required long-running CENTRM pointwise slowing down calculations. FAST, the US Nuclear Regulatory Commission (NRC) fuel performance code, is being coupled with the SCALE code package for neutronic calculation, which requires very fast cross section processing for multiple fuel zones with nonuniform temperature distribution. The XSProc-BONAMI procedure is very fast, but it does not work for the specified problem because the Bondarenko resonance self-shielding method in BONAMI does not produce correct self-shielded multigroup cross sections for multiple fuel rings with nonuniform temperature profiles. A spatially dependent self-shielding method based on Dancoff factors has been implemented into BONAMI to correctly predict local powers inside fuel pellets, as well as eigenvalue for multiple fuel zones for uniform and nonuniform temperature distributions. Implementing the new method drastically improves prediction of multiplication factors and fission densities compared to results obtained with the reference continuous-energy Monte Carlo calculations.

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	2325-2331
Number of pages	7
ISBN (Electronic)	9781713886310
DOIs	https://doi.org/10.13182/M&C21-33765
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

BONAMI
Spatially dependent self-shielding
nonuniform temperature

Access to Document

10.13182/M&C21-33765

Cite this

Kim, K. S., Holcomb, A. M., & Wieselquist, W. A. (2021). SPATIALLY DEPENDENT RESONANCE SELF-SHIELDING CAPABILITY FOR NON-UNIFORM TEMPERATURE PROFILE IN SCALE-6.3 XSPROC-BONAMI. In Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021 (pp. 2325-2331). (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&C21-33765

Kim, Kang Seog ; Holcomb, Andrew M. ; Wieselquist, William A. / SPATIALLY DEPENDENT RESONANCE SELF-SHIELDING CAPABILITY FOR NON-UNIFORM TEMPERATURE PROFILE IN SCALE-6.3 XSPROC-BONAMI. 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. 2325-2331 (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 = "SPATIALLY DEPENDENT RESONANCE SELF-SHIELDING CAPABILITY FOR NON-UNIFORM TEMPERATURE PROFILE IN SCALE-6.3 XSPROC-BONAMI",

abstract = "For some fuel depletion and performance simulations, temperature-dependent rings of fuel are preferred. This has typically required long-running CENTRM pointwise slowing down calculations. FAST, the US Nuclear Regulatory Commission (NRC) fuel performance code, is being coupled with the SCALE code package for neutronic calculation, which requires very fast cross section processing for multiple fuel zones with nonuniform temperature distribution. The XSProc-BONAMI procedure is very fast, but it does not work for the specified problem because the Bondarenko resonance self-shielding method in BONAMI does not produce correct self-shielded multigroup cross sections for multiple fuel rings with nonuniform temperature profiles. A spatially dependent self-shielding method based on Dancoff factors has been implemented into BONAMI to correctly predict local powers inside fuel pellets, as well as eigenvalue for multiple fuel zones for uniform and nonuniform temperature distributions. Implementing the new method drastically improves prediction of multiplication factors and fission densities compared to results obtained with the reference continuous-energy Monte Carlo calculations.",

keywords = "BONAMI, Spatially dependent self-shielding, nonuniform temperature",

author = "Kim, {Kang Seog} and Holcomb, {Andrew M.} 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&C21-33765",

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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pages = "2325--2331",

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Kim, KS , Holcomb, AM & Wieselquist, WA 2021, SPATIALLY DEPENDENT RESONANCE SELF-SHIELDING CAPABILITY FOR NON-UNIFORM TEMPERATURE PROFILE IN SCALE-6.3 XSPROC-BONAMI. 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. 2325-2331, 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&C21-33765

SPATIALLY DEPENDENT RESONANCE SELF-SHIELDING CAPABILITY FOR NON-UNIFORM TEMPERATURE PROFILE IN SCALE-6.3 XSPROC-BONAMI. / Kim, Kang Seog ; Holcomb, Andrew M.; Wieselquist, William A.
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. 2325-2331 (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 - Holcomb, Andrew M.

AU - Wieselquist, William A.

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N2 - For some fuel depletion and performance simulations, temperature-dependent rings of fuel are preferred. This has typically required long-running CENTRM pointwise slowing down calculations. FAST, the US Nuclear Regulatory Commission (NRC) fuel performance code, is being coupled with the SCALE code package for neutronic calculation, which requires very fast cross section processing for multiple fuel zones with nonuniform temperature distribution. The XSProc-BONAMI procedure is very fast, but it does not work for the specified problem because the Bondarenko resonance self-shielding method in BONAMI does not produce correct self-shielded multigroup cross sections for multiple fuel rings with nonuniform temperature profiles. A spatially dependent self-shielding method based on Dancoff factors has been implemented into BONAMI to correctly predict local powers inside fuel pellets, as well as eigenvalue for multiple fuel zones for uniform and nonuniform temperature distributions. Implementing the new method drastically improves prediction of multiplication factors and fission densities compared to results obtained with the reference continuous-energy Monte Carlo calculations.

AB - For some fuel depletion and performance simulations, temperature-dependent rings of fuel are preferred. This has typically required long-running CENTRM pointwise slowing down calculations. FAST, the US Nuclear Regulatory Commission (NRC) fuel performance code, is being coupled with the SCALE code package for neutronic calculation, which requires very fast cross section processing for multiple fuel zones with nonuniform temperature distribution. The XSProc-BONAMI procedure is very fast, but it does not work for the specified problem because the Bondarenko resonance self-shielding method in BONAMI does not produce correct self-shielded multigroup cross sections for multiple fuel rings with nonuniform temperature profiles. A spatially dependent self-shielding method based on Dancoff factors has been implemented into BONAMI to correctly predict local powers inside fuel pellets, as well as eigenvalue for multiple fuel zones for uniform and nonuniform temperature distributions. Implementing the new method drastically improves prediction of multiplication factors and fission densities compared to results obtained with the reference continuous-energy Monte Carlo calculations.

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M3 - Conference contribution

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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

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Kim KS , Holcomb AM , Wieselquist WA. SPATIALLY DEPENDENT RESONANCE SELF-SHIELDING CAPABILITY FOR NON-UNIFORM TEMPERATURE PROFILE IN SCALE-6.3 XSPROC-BONAMI. 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. 2325-2331. (Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021). doi: 10.13182/M&C21-33765

SPATIALLY DEPENDENT RESONANCE SELF-SHIELDING CAPABILITY FOR NON-UNIFORM TEMPERATURE PROFILE IN SCALE-6.3 XSPROC-BONAMI

Abstract

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Keywords

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