Direct Calculation of Safety-Related Parameters for Coupled Transients Using Monte Carlo Neutronics Plus Subchannel Thermal-Hydraulics

Diego Ferraro; Manuel García; Ville Valtavirta; Uwe Imke; Riku Tuominen; Jaakko Leppänen; Sanchez-Espinoza Victor

Direct Calculation of Safety-Related Parameters for Coupled Transients Using Monte Carlo Neutronics Plus Subchannel Thermal-Hydraulics

Diego Ferraro^*
, Manuel García
, Ville Valtavirta
, Uwe Imke
, Riku Tuominen
, Jaakko Leppänen
, Sanchez-Espinoza Victor

^*Corresponding author for this work

BA4501 Reactor analysis

Karlsruhe Institute of Technology (KIT)

Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review

1 Citation (Scopus)

Abstract

The recent development of high-fidelity coupled neutronic-thermalhydraulic tools based in Montecarlo (MC) transport codes provides a complete independent calculation alternative for a wide range of safety-related parameters within light water reactors (LWR). In particular, the application of such approach for short-time coupled transients at full-scope models represents a compelling work path. A novel implementation of a coupled tool between the well-known Serpent 2 (MC neutronics) and SUBCHANFLOW (subchannel TH) codes is here used to study short time RIA-kind scenarios (i.e. Reactivity Initiated Accidents) in SPERT-IIIE reactor, showing the aptness of this approach to obtain key safety-parameters for coupled transients within a realistic PWR geometry and operational conditions avoiding almost all traditional approximations.

Original language	English
Title of host publication	Mathematics & Computation (M&C) 2021
Publisher	American Nuclear Society (ANS)
Pages	549-558
ISBN (Electronic)	978-1-71388-631-0
Publication status	Published - 2021
MoE publication type	A4 Article in a conference publication
Event	International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2021 - Virtual, Raleigh, United States Duration: 11 Apr 2021 → 15 Apr 2021

Publication series

Series	Transactions of the American Nuclear Society
Number	3141
ISSN	0003-018X

Conference

Conference	International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2021
Country/Territory	United States
City	Raleigh
Period	11/04/21 → 15/04/21

Funding

This work was done within the McSAFE project which is receiving funding from the Euratom research and training programme 2014-2018 under grant agreement No 755097. This work was performed on the computational resource ForHLR II, funded by the Ministry of Science, Research and the Arts Baden-Württemberg and DFG (”Deutsche Forschungsgemeinschaft”).

Keywords

coupled transients
Monte Carlo
Serpent 2
SPERT-IIIE

Access to Document

https://www.ans.org/pubs/proceedings/article-50027/

Cite this

Ferraro, D., García, M., Valtavirta, V., Imke, U., Tuominen, R., Leppänen, J., & Victor, S.-E. (2021). Direct Calculation of Safety-Related Parameters for Coupled Transients Using Monte Carlo Neutronics Plus Subchannel Thermal-Hydraulics. In Mathematics & Computation (M&C) 2021 (pp. 549-558). Article 50027 American Nuclear Society (ANS). https://www.ans.org/pubs/proceedings/article-50027/

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title = "Direct Calculation of Safety-Related Parameters for Coupled Transients Using Monte Carlo Neutronics Plus Subchannel Thermal-Hydraulics",

abstract = "The recent development of high-fidelity coupled neutronic-thermalhydraulic tools based in Montecarlo (MC) transport codes provides a complete independent calculation alternative for a wide range of safety-related parameters within light water reactors (LWR). In particular, the application of such approach for short-time coupled transients at full-scope models represents a compelling work path. A novel implementation of a coupled tool between the well-known Serpent 2 (MC neutronics) and SUBCHANFLOW (subchannel TH) codes is here used to study short time RIA-kind scenarios (i.e. Reactivity Initiated Accidents) in SPERT-IIIE reactor, showing the aptness of this approach to obtain key safety-parameters for coupled transients within a realistic PWR geometry and operational conditions avoiding almost all traditional approximations.",

keywords = "coupled transients, Monte Carlo, Serpent 2, SPERT-IIIE",

author = "Diego Ferraro and Manuel Garc{\'i}a and Ville Valtavirta and Uwe Imke and Riku Tuominen and Jaakko Lepp{\"a}nen and Sanchez-Espinoza Victor",

note = "Publisher Copyright: Copyright {\textcopyright} 2021 AMERICAN NUCLEAR SOCIETY, INCORPORATED, LA GRANGE PARK, ILLINOIS 60526.All rights reserved.; International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M\&C 2021 ; Conference date: 11-04-2021 Through 15-04-2021",

year = "2021",

language = "English",

series = "Transactions of the American Nuclear Society",

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Ferraro, D, García, M, Valtavirta, V, Imke, U, Tuominen, R , Leppänen, J & Victor, S-E 2021, Direct Calculation of Safety-Related Parameters for Coupled Transients Using Monte Carlo Neutronics Plus Subchannel Thermal-Hydraulics. in Mathematics & Computation (M&C) 2021., 50027, American Nuclear Society (ANS), Transactions of the American Nuclear Society, no. 3141, pp. 549-558, International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2021, Raleigh, North Carolina, United States, 11/04/21. <https://www.ans.org/pubs/proceedings/article-50027/>

Direct Calculation of Safety-Related Parameters for Coupled Transients Using Monte Carlo Neutronics Plus Subchannel Thermal-Hydraulics. / Ferraro, Diego; García, Manuel; Valtavirta, Ville et al.
Mathematics & Computation (M&C) 2021. American Nuclear Society (ANS), 2021. p. 549-558 50027 (Transactions of the American Nuclear Society; No. 3141).

Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review

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T1 - Direct Calculation of Safety-Related Parameters for Coupled Transients Using Monte Carlo Neutronics Plus Subchannel Thermal-Hydraulics

AU - Ferraro, Diego

AU - García, Manuel

AU - Valtavirta, Ville

AU - Imke, Uwe

AU - Tuominen, Riku

AU - Leppänen, Jaakko

AU - Victor, Sanchez-Espinoza

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AB - The recent development of high-fidelity coupled neutronic-thermalhydraulic tools based in Montecarlo (MC) transport codes provides a complete independent calculation alternative for a wide range of safety-related parameters within light water reactors (LWR). In particular, the application of such approach for short-time coupled transients at full-scope models represents a compelling work path. A novel implementation of a coupled tool between the well-known Serpent 2 (MC neutronics) and SUBCHANFLOW (subchannel TH) codes is here used to study short time RIA-kind scenarios (i.e. Reactivity Initiated Accidents) in SPERT-IIIE reactor, showing the aptness of this approach to obtain key safety-parameters for coupled transients within a realistic PWR geometry and operational conditions avoiding almost all traditional approximations.

KW - coupled transients

KW - Monte Carlo

KW - Serpent 2

KW - SPERT-IIIE

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BT - Mathematics & Computation (M&C) 2021

PB - American Nuclear Society (ANS)

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

Y2 - 11 April 2021 through 15 April 2021

ER -

Direct Calculation of Safety-Related Parameters for Coupled Transients Using Monte Carlo Neutronics Plus Subchannel Thermal-Hydraulics

Abstract

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Conference

Funding

Keywords

Access to Document

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