On the simulation of neutron noise induced by vibrations of fuel pins in a fuel assembly

[EN] Vibrations of fuel assemblies are an important issue in the safe operation of nuclear reactors, because they can challenge the integrity of the fuel with potential for radioactive releases. Reactor neutron noise-based techniques for monitoring vibrations are valuable for core diagnostic since t...

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Detalhes bibliográficos
Autores: Vinai, P., Yi, H., Demazière, C., Rouchon, A., Zoia, A., Vidal-Ferràndiz, Antoni|||0000-0001-5449-7356, Carreño, Amanda|||0000-0003-2302-1157, Ginestar Peiro, Damián|||0000-0003-1243-6648, Verdú Martín, Gumersindo Jesús|||0000-0001-5098-080X
Formato: artículo
Fecha de publicación:2023
País:España
Recursos:Universitat Politècnica de València (UPV)
Repositorio:RiuNet. Repositorio Institucional de la Universitat Politécnica de Valéncia
Idioma:inglés
OAI Identifier:oai:riunet.upv.es:10251/205031
Acesso em linha:https://riunet.upv.es/handle/10251/205031
Access Level:acceso abierto
Palavra-chave:Reactor neutron noise modelling
Monte Carlo
Deterministic transport methods
Diffusion
FISICA APLICADA
INGENIERIA NUCLEAR
MATEMATICA APLICADA
Descrição
Resumo:[EN] Vibrations of fuel assemblies are an important issue in the safe operation of nuclear reactors, because they can challenge the integrity of the fuel with potential for radioactive releases. Reactor neutron noise-based techniques for monitoring vibrations are valuable for core diagnostic since they are not intrusive and make use of ordinary neutron flux measurements from ex-core and in-core detectors. The application of these techniques involves the solution of inverse problems that require numerical simulations capable of estimating the reactor neutron noise, given a model of the vibrations. For this purpose, several novel reactor neutron noise solvers have been developed in the CORTEX project using either Monte Carlo or deterministic methods, such as the discrete or-dinates method, the method of characteristics, and the diffusion approximation. In the current work, these solvers have been scrutinized by computing the neutron noise induced by vibrations of one or multiple fuel pins in a simplified UOX fuel assembly benchmark, via proper variations of macroscopic neutron cross sections. The comparison of these neutron noise solutions obtained from the different methods shows novel insights into the simulation of neutron noise induced by mechanical vibrations, such as the challenges posed by the Monte Carlo method, the impact of the angular discretization on the application of the discrete ordinates method, and the accuracy of the diffusion approximation assessed via the higher-order neutron transport methods.