Application of nuclear data covariance matrices to representativity calculations

Federico Grimaldi; Patrick D. Blaise; Luca Fiorito; Anatoly Kochetkov; Antonin Krása; Pierre-Etienne Labeau; Pablo Romojaro; Gert Van den Eynde; Guido Vittiglio; Jan Wagemans

doi:10.1051/epjconf/202429405005

Application of nuclear data covariance matrices to representativity calculations

Federico Grimaldi, Patrick D. Blaise, Luca Fiorito, Anatoly Kochetkov, Antonin Krása, Pierre-Etienne Labeau, Pablo Romojaro, Gert Van den Eynde, Guido Vittiglio, Jan Wagemans

Nuclear Systems Measurements

Research output › peer-review

Abstract

The neutronics design of new reactors has been historically relying on zero power research reactors for the simulation of the core irradiation conditions as well as for nuclear data and code validation. In this framework, a study on the possible MYRRHA representativity improvement coming from the loading of MOX fuel in VENUS-F zero power reactor is under investigation. This work analyses the effect of the nuclear data used in the sensitivity and representativity calculations, highlighting the need for a comprehensive set of nuclides and reactions to be further studied.

Original language	English
Title of host publication	EPJ Web of Conf.
Publisher	EDP Sciences
Number of pages	7
Volume	294
Edition	2024
DOIs	https://doi.org/10.1051/epjconf/202429405005
State	Published - 17 Apr 2024
Event	2023 - WONDER: 6th International Workshop On Nuclear Data Evaluation for Reactor applications - Hôtel Aquabella, d'Aix-en-Provence Duration: 5 Jun 2023 → 9 Jun 2023

Publication series

Name	EPJ Web of Conf.
Publisher	EDP Sciences
ISSN (Electronic)	2100-014X

Workshop

Workshop	2023 - WONDER
Country/Territory	France
City	d'Aix-en-Provence
Period	2023-06-05 → 2023-06-09

Access to Document

10.1051/epjconf/202429405005License: Unspecified

Cite this

Grimaldi, F., Blaise, P. D., Fiorito, L., Kochetkov, A., Krása, A., Labeau, P.-E., Romojaro, P., Van den Eynde, G., Vittiglio, G., & Wagemans, J. (2024). Application of nuclear data covariance matrices to representativity calculations. In EPJ Web of Conf. (2024 ed., Vol. 294). Article 05005 (EPJ Web of Conf. ). EDP Sciences. https://doi.org/10.1051/epjconf/202429405005

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title = "Application of nuclear data covariance matrices to representativity calculations",

abstract = "The neutronics design of new reactors has been historically relying on zero power research reactors for the simulation of the core irradiation conditions as well as for nuclear data and code validation. In this framework, a study on the possible MYRRHA representativity improvement coming from the loading of MOX fuel in VENUS-F zero power reactor is under investigation. This work analyses the effect of the nuclear data used in the sensitivity and representativity calculations, highlighting the need for a comprehensive set of nuclides and reactions to be further studied.",

keywords = "Nuclear data, Fast reactor, Representativity calculation",

author = "Federico Grimaldi and Blaise, {Patrick D.} and Luca Fiorito and Anatoly Kochetkov and Antonin Kr{\'a}sa and Pierre-Etienne Labeau and Pablo Romojaro and {Van den Eynde}, Gert and Guido Vittiglio and Jan Wagemans",

note = "Score=3; 2023 - WONDER : 6th International Workshop On Nuclear Data Evaluation for Reactor applications ; Conference date: 05-06-2023 Through 09-06-2023",

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Grimaldi, F, Blaise, PD, Fiorito, L , Kochetkov, A , Krása, A, Labeau, P-E, Romojaro, P , Van den Eynde, G , Vittiglio, G & Wagemans, J 2024, Application of nuclear data covariance matrices to representativity calculations. in EPJ Web of Conf.. 2024 edn, vol. 294, 05005, EPJ Web of Conf. , EDP Sciences, 2023 - WONDER, d'Aix-en-Provence, France, 2023-06-05. https://doi.org/10.1051/epjconf/202429405005

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AU - Grimaldi, Federico

AU - Blaise, Patrick D.

AU - Fiorito, Luca

AU - Kochetkov, Anatoly

AU - Krása, Antonin

AU - Labeau, Pierre-Etienne

AU - Romojaro, Pablo

AU - Van den Eynde, Gert

AU - Vittiglio, Guido

AU - Wagemans, Jan

N1 - Score=3

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Y1 - 2024/4/17

N2 - The neutronics design of new reactors has been historically relying on zero power research reactors for the simulation of the core irradiation conditions as well as for nuclear data and code validation. In this framework, a study on the possible MYRRHA representativity improvement coming from the loading of MOX fuel in VENUS-F zero power reactor is under investigation. This work analyses the effect of the nuclear data used in the sensitivity and representativity calculations, highlighting the need for a comprehensive set of nuclides and reactions to be further studied.

AB - The neutronics design of new reactors has been historically relying on zero power research reactors for the simulation of the core irradiation conditions as well as for nuclear data and code validation. In this framework, a study on the possible MYRRHA representativity improvement coming from the loading of MOX fuel in VENUS-F zero power reactor is under investigation. This work analyses the effect of the nuclear data used in the sensitivity and representativity calculations, highlighting the need for a comprehensive set of nuclides and reactions to be further studied.

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KW - Fast reactor

KW - Representativity calculation

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T3 - EPJ Web of Conf.

BT - EPJ Web of Conf.

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T2 - 2023 - WONDER

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