Coupling of dynamic Monte Carlo with thermal-hydraulic feedback

Bart Sjenitzer; Jan Eduard Hoogenboom; Javier Jiménez Escalante; Victor Hugo Sánchez Espinoza

doi:10.1016/j.anucene.2014.09.018

Coupling of dynamic Monte Carlo with thermal-hydraulic feedback

Bart Sjenitzer, Jan Eduard Hoogenboom, Javier Jiménez Escalante, Victor Hugo Sánchez Espinoza

Research output › peer-review

44 Scopus citations

Abstract

Transient analysis of nuclear reactors is traditionally the domain of deterministic methods, even tough these methods are known to have limitations. With the development of dynamic Monte Carlo and the development of coupled-steady state Monte Carlo calculations the road has been paved to perform transient analysis of high power reactors using Monte Carlo. By this way, it is possible to take into account the thermal-hydraulic feedback, while the neutron transport is modelled in full detail. In this paper a new method is described, which can perform such stochastic analysis of a transient scenario.

Original language	English
Pages (from-to)	27-39
Number of pages	13
Journal	Annals of nuclear energy
Volume	76
DOIs	https://doi.org/10.1016/j.anucene.2014.09.018
State	Published - Feb 2015

ASJC Scopus subject areas

Nuclear Energy and Engineering

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10.1016/j.anucene.2014.09.018License: Unspecified

Cite this

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title = "Coupling of dynamic Monte Carlo with thermal-hydraulic feedback",

abstract = "Transient analysis of nuclear reactors is traditionally the domain of deterministic methods, even tough these methods are known to have limitations. With the development of dynamic Monte Carlo and the development of coupled-steady state Monte Carlo calculations the road has been paved to perform transient analysis of high power reactors using Monte Carlo. By this way, it is possible to take into account the thermal-hydraulic feedback, while the neutron transport is modelled in full detail. In this paper a new method is described, which can perform such stochastic analysis of a transient scenario.",

keywords = "Coupled calculation, Feedback, Monte Carlo, Neutron transport, Thermal-hydraulics",

author = "Bart Sjenitzer and Hoogenboom, {Jan Eduard} and {Jim{\'e}nez Escalante}, Javier and {S{\'a}nchez Espinoza}, {Victor Hugo}",

note = "Funding Information: This work is partially funded by the Integrated Project NURISP (contract n o 232124) in the 7th Euratom Framework Programme of the European Union. Publisher Copyright: {\textcopyright} 2014 Elsevier Ltd. All rights reserved.",

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AU - Sjenitzer, Bart

AU - Hoogenboom, Jan Eduard

AU - Jiménez Escalante, Javier

AU - Sánchez Espinoza, Victor Hugo

N1 - Funding Information: This work is partially funded by the Integrated Project NURISP (contract n o 232124) in the 7th Euratom Framework Programme of the European Union. Publisher Copyright: © 2014 Elsevier Ltd. All rights reserved.

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N2 - Transient analysis of nuclear reactors is traditionally the domain of deterministic methods, even tough these methods are known to have limitations. With the development of dynamic Monte Carlo and the development of coupled-steady state Monte Carlo calculations the road has been paved to perform transient analysis of high power reactors using Monte Carlo. By this way, it is possible to take into account the thermal-hydraulic feedback, while the neutron transport is modelled in full detail. In this paper a new method is described, which can perform such stochastic analysis of a transient scenario.

AB - Transient analysis of nuclear reactors is traditionally the domain of deterministic methods, even tough these methods are known to have limitations. With the development of dynamic Monte Carlo and the development of coupled-steady state Monte Carlo calculations the road has been paved to perform transient analysis of high power reactors using Monte Carlo. By this way, it is possible to take into account the thermal-hydraulic feedback, while the neutron transport is modelled in full detail. In this paper a new method is described, which can perform such stochastic analysis of a transient scenario.

KW - Coupled calculation

KW - Feedback

KW - Monte Carlo

KW - Neutron transport

KW - Thermal-hydraulics

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