IMPLEMENTATION OF GENERALIZED INCORE DETECTOR RESPONSES IN MPACT

Erik Walker; Shane Stimpson; Benjamin Collins; Andrew Godfrey; James Eller

doi:10.13182/M&C21-33884

IMPLEMENTATION OF GENERALIZED INCORE DETECTOR RESPONSES IN MPACT

Erik Walker
, Shane Stimpson
, Benjamin Collins
, Andrew Godfrey
, James Eller

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

Abstract

In this paper, the performance of a new detector response methodology is examined. The new capability, implemented in the MPACT deterministic neutron transport solver, allows for incore detector responses to be calculated on an arbitrary axial mesh that is not limited to the computational axial meshing. A single miniaturized 3D fuel assembly is used to compare the old and new methods. The 3×3 assembly had radial reflective boundary conditions and contained five spacer grids along its axial length. The results from this study show that the new methodology allows the calculation of finer incore detector responses, which can better describe localized flux shapes without increasing the simulation runtime. The axial reflection at the top and bottom of the core, as well as the flux depression in the area surrounding spacer grids, are more accurately represented using this new methodology. In addition to the test problem, a full-core model is compared with measured 600-level data from the Catawba Nuclear Station Unit 1 for cycle 19. This comparison resulted in a 3D RMS of 4.8% at the start of the cycle, which was reduced to 2.2% at the end of cycle. Owing to the uncertainty in the measurement, these results demonstrate good agreement with the simulated MPACT response. Although these results are only marginally better than linearly interpolating data using the existing methodology, more work is ongoing to further improve the calculated detector response.

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	1204-1214
Number of pages	11
ISBN (Electronic)	9781713886310
DOIs	https://doi.org/10.13182/M&C21-33884
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 made use of Idaho National aborL atory computing resources, which are supported by the Office of Nuclear Energy of the US Department of Energy and the Nuclear Science User Facilities under Contract No. DE-AC07 -05ID14517. 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). 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 made use of Idaho National Laboratory computing resources, which are supported by the Office of Nuclear Energy of the US Department of Energy and the Nuclear Science User Facilities under Contract No. DE-AC07-05ID14517. The authors thank the Duke Energy Corporation for providing the data used in generating the model and the 600-level detector response data used in the analysis.

Keywords

Detector Response
MPACT
VERA

Access to Document

10.13182/M&C21-33884

Cite this

Walker, E., Stimpson, S., Collins, B., Godfrey, A., & Eller, J. (2021). IMPLEMENTATION OF GENERALIZED INCORE DETECTOR RESPONSES IN MPACT. In Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021 (pp. 1204-1214). (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&C21-33884

Walker, Erik ; Stimpson, Shane ; Collins, Benjamin et al. / IMPLEMENTATION OF GENERALIZED INCORE DETECTOR RESPONSES IN MPACT. 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. 1204-1214 (Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021).

@inproceedings{c8216d962967429c89c1e59b9efb8fc7,

title = "IMPLEMENTATION OF GENERALIZED INCORE DETECTOR RESPONSES IN MPACT",

abstract = "In this paper, the performance of a new detector response methodology is examined. The new capability, implemented in the MPACT deterministic neutron transport solver, allows for incore detector responses to be calculated on an arbitrary axial mesh that is not limited to the computational axial meshing. A single miniaturized 3D fuel assembly is used to compare the old and new methods. The 3×3 assembly had radial reflective boundary conditions and contained five spacer grids along its axial length. The results from this study show that the new methodology allows the calculation of finer incore detector responses, which can better describe localized flux shapes without increasing the simulation runtime. The axial reflection at the top and bottom of the core, as well as the flux depression in the area surrounding spacer grids, are more accurately represented using this new methodology. In addition to the test problem, a full-core model is compared with measured 600-level data from the Catawba Nuclear Station Unit 1 for cycle 19. This comparison resulted in a 3D RMS of 4.8\% at the start of the cycle, which was reduced to 2.2\% at the end of cycle. Owing to the uncertainty in the measurement, these results demonstrate good agreement with the simulated MPACT response. Although these results are only marginally better than linearly interpolating data using the existing methodology, more work is ongoing to further improve the calculated detector response.",

keywords = "Detector Response, MPACT, VERA",

author = "Erik Walker and Shane Stimpson and Benjamin Collins and Andrew Godfrey and James Eller",

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\&C21-33884",

language = "English",

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

publisher = "American Nuclear Society",

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Walker, E, Stimpson, S, Collins, B, Godfrey, A & Eller, J 2021, IMPLEMENTATION OF GENERALIZED INCORE DETECTOR RESPONSES IN MPACT. 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. 1204-1214, 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&C21-33884

IMPLEMENTATION OF GENERALIZED INCORE DETECTOR RESPONSES IN MPACT. / Walker, Erik; Stimpson, Shane; Collins, Benjamin 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. 1204-1214 (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

TY - GEN

T1 - IMPLEMENTATION OF GENERALIZED INCORE DETECTOR RESPONSES IN MPACT

AU - Walker, Erik

AU - Stimpson, Shane

AU - Collins, Benjamin

AU - Godfrey, Andrew

AU - Eller, James

PY - 2021

Y1 - 2021

N2 - In this paper, the performance of a new detector response methodology is examined. The new capability, implemented in the MPACT deterministic neutron transport solver, allows for incore detector responses to be calculated on an arbitrary axial mesh that is not limited to the computational axial meshing. A single miniaturized 3D fuel assembly is used to compare the old and new methods. The 3×3 assembly had radial reflective boundary conditions and contained five spacer grids along its axial length. The results from this study show that the new methodology allows the calculation of finer incore detector responses, which can better describe localized flux shapes without increasing the simulation runtime. The axial reflection at the top and bottom of the core, as well as the flux depression in the area surrounding spacer grids, are more accurately represented using this new methodology. In addition to the test problem, a full-core model is compared with measured 600-level data from the Catawba Nuclear Station Unit 1 for cycle 19. This comparison resulted in a 3D RMS of 4.8% at the start of the cycle, which was reduced to 2.2% at the end of cycle. Owing to the uncertainty in the measurement, these results demonstrate good agreement with the simulated MPACT response. Although these results are only marginally better than linearly interpolating data using the existing methodology, more work is ongoing to further improve the calculated detector response.

AB - In this paper, the performance of a new detector response methodology is examined. The new capability, implemented in the MPACT deterministic neutron transport solver, allows for incore detector responses to be calculated on an arbitrary axial mesh that is not limited to the computational axial meshing. A single miniaturized 3D fuel assembly is used to compare the old and new methods. The 3×3 assembly had radial reflective boundary conditions and contained five spacer grids along its axial length. The results from this study show that the new methodology allows the calculation of finer incore detector responses, which can better describe localized flux shapes without increasing the simulation runtime. The axial reflection at the top and bottom of the core, as well as the flux depression in the area surrounding spacer grids, are more accurately represented using this new methodology. In addition to the test problem, a full-core model is compared with measured 600-level data from the Catawba Nuclear Station Unit 1 for cycle 19. This comparison resulted in a 3D RMS of 4.8% at the start of the cycle, which was reduced to 2.2% at the end of cycle. Owing to the uncertainty in the measurement, these results demonstrate good agreement with the simulated MPACT response. Although these results are only marginally better than linearly interpolating data using the existing methodology, more work is ongoing to further improve the calculated detector response.

KW - Detector Response

KW - MPACT

KW - VERA

UR - https://www.scopus.com/pages/publications/85183596841

U2 - 10.13182/M&C21-33884

DO - 10.13182/M&C21-33884

M3 - Conference contribution

AN - SCOPUS:85183596841

T3 - Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021

SP - 1204

EP - 1214

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

T2 - 2021 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021

Y2 - 3 October 2021 through 7 October 2021

ER -

Walker E, Stimpson S, Collins B, Godfrey A, Eller J. IMPLEMENTATION OF GENERALIZED INCORE DETECTOR RESPONSES IN MPACT. 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. 1204-1214. (Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021). doi: 10.13182/M&C21-33884

IMPLEMENTATION OF GENERALIZED INCORE DETECTOR RESPONSES IN MPACT

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