Whole-core validation of the Superphenix reactor using WIMS11 and an investigation into a hybrid RZ-HEX SP3 calculation route

Una Davies; Ben Lindley; Brendan Tollit; Eugene Shwageraus

Whole-core validation of the Superphenix reactor using WIMS11 and an investigation into a hybrid RZ-HEX SP3 calculation route

Una Davies, Ben Lindley, Brendan Tollit, Eugene Shwageraus

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

3 Scopus citations

Abstract

The Superphénix SFR has been modelled using the new MERLIN flux solver module of the WIMS reactor physics code. The reactor was simulated for a range of calculation cases which investigated the neutronic effects of different temperatures and control rod insertions, for the purposes of validation against experimental data and verification against a Serpent benchmark. The WIMS results were found to be in good agreement with the experimental data and the Serpent results. Two different MERLIN models were constructed: a detailed hexagonal-Z geometry in 172 groups, and a hybrid method which used a simplified RZ model to condense the data used in the calculation into fewer groups before using the full hexagonal-Z geometry. This hybrid method was found to decrease the time taken for the calculations by a factor of five while retaining a good level of accuracy.

Original language	English
Title of host publication	International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019
Publisher	American Nuclear Society
Pages	1198-1207
Number of pages	10
ISBN (Electronic)	9780894487699
State	Published - 1 Jan 2019
Externally published	Yes
Event	2019 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019 - Portland, United States Duration: 25 Aug 2019 → 29 Aug 2019

Publication series

Name	International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019

Conference

Conference	2019 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019
Country/Territory	United States
City	Portland
Period	25/08/19 → 29/08/19

Keywords

SP3
Sodium-cooled fast reactor
Superphenix

Cite this

Davies, U., Lindley, B., Tollit, B., & Shwageraus, E. (2019). Whole-core validation of the Superphenix reactor using WIMS11 and an investigation into a hybrid RZ-HEX SP3 calculation route. In International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019 (pp. 1198-1207). (International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019). American Nuclear Society.

Davies, Una ; Lindley, Ben ; Tollit, Brendan ; Shwageraus, Eugene. / Whole-core validation of the Superphenix reactor using WIMS11 and an investigation into a hybrid RZ-HEX SP3 calculation route. International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019. American Nuclear Society, 2019. pp. 1198-1207 (International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019).

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title = "Whole-core validation of the Superphenix reactor using WIMS11 and an investigation into a hybrid RZ-HEX SP3 calculation route",

abstract = "The Superph{\'e}nix SFR has been modelled using the new MERLIN flux solver module of the WIMS reactor physics code. The reactor was simulated for a range of calculation cases which investigated the neutronic effects of different temperatures and control rod insertions, for the purposes of validation against experimental data and verification against a Serpent benchmark. The WIMS results were found to be in good agreement with the experimental data and the Serpent results. Two different MERLIN models were constructed: a detailed hexagonal-Z geometry in 172 groups, and a hybrid method which used a simplified RZ model to condense the data used in the calculation into fewer groups before using the full hexagonal-Z geometry. This hybrid method was found to decrease the time taken for the calculations by a factor of five while retaining a good level of accuracy.",

keywords = "SP3, Sodium-cooled fast reactor, Superphenix",

author = "Una Davies and Ben Lindley and Brendan Tollit and Eugene Shwageraus",

note = "Funding Information: This work has been prepared within EU Project ESFR-SMART which has received funding from the EURATOM Research and Training Programme 2014-2018 under the Grant Agreement No. 754501. Publisher Copyright: {\textcopyright} 2019 American Nuclear Society. All rights reserved.; 2019 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019 ; Conference date: 25-08-2019 Through 29-08-2019",

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series = "International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019",

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Davies, U, Lindley, B, Tollit, B & Shwageraus, E 2019, Whole-core validation of the Superphenix reactor using WIMS11 and an investigation into a hybrid RZ-HEX SP3 calculation route. in International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019. International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019, American Nuclear Society, pp. 1198-1207, 2019 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019, Portland, United States, 25/08/19.

Whole-core validation of the Superphenix reactor using WIMS11 and an investigation into a hybrid RZ-HEX SP3 calculation route. / Davies, Una; Lindley, Ben; Tollit, Brendan; Shwageraus, Eugene.

International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019. American Nuclear Society, 2019. p. 1198-1207 (International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019).

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

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AU - Davies, Una

AU - Lindley, Ben

AU - Tollit, Brendan

AU - Shwageraus, Eugene

N1 - Funding Information: This work has been prepared within EU Project ESFR-SMART which has received funding from the EURATOM Research and Training Programme 2014-2018 under the Grant Agreement No. 754501. Publisher Copyright: © 2019 American Nuclear Society. All rights reserved.

PY - 2019/1/1

Y1 - 2019/1/1

N2 - The Superphénix SFR has been modelled using the new MERLIN flux solver module of the WIMS reactor physics code. The reactor was simulated for a range of calculation cases which investigated the neutronic effects of different temperatures and control rod insertions, for the purposes of validation against experimental data and verification against a Serpent benchmark. The WIMS results were found to be in good agreement with the experimental data and the Serpent results. Two different MERLIN models were constructed: a detailed hexagonal-Z geometry in 172 groups, and a hybrid method which used a simplified RZ model to condense the data used in the calculation into fewer groups before using the full hexagonal-Z geometry. This hybrid method was found to decrease the time taken for the calculations by a factor of five while retaining a good level of accuracy.

AB - The Superphénix SFR has been modelled using the new MERLIN flux solver module of the WIMS reactor physics code. The reactor was simulated for a range of calculation cases which investigated the neutronic effects of different temperatures and control rod insertions, for the purposes of validation against experimental data and verification against a Serpent benchmark. The WIMS results were found to be in good agreement with the experimental data and the Serpent results. Two different MERLIN models were constructed: a detailed hexagonal-Z geometry in 172 groups, and a hybrid method which used a simplified RZ model to condense the data used in the calculation into fewer groups before using the full hexagonal-Z geometry. This hybrid method was found to decrease the time taken for the calculations by a factor of five while retaining a good level of accuracy.

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KW - Sodium-cooled fast reactor

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BT - International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019

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Davies U, Lindley B, Tollit B, Shwageraus E. Whole-core validation of the Superphenix reactor using WIMS11 and an investigation into a hybrid RZ-HEX SP3 calculation route. In International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019. American Nuclear Society. 2019. p. 1198-1207. (International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019).

Whole-core validation of the Superphenix reactor using WIMS11 and an investigation into a hybrid RZ-HEX SP3 calculation route

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Publication series

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Keywords

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