Uncertainty and sensitivity of neutron kinetic parameters in the dynamic response of a PWR rod ejection accident coupled simulation
In nuclear safety analysis, it is very important to be able to simulate the different transients that can occur in a nuclear power plant with a very high accuracy. Although the best estimate codes can simulate the transients and provide realistic system responses, the use of nonexactmodels, together...
| Autores: | , , , , , , |
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| Tipo de documento: | artigo |
| Data de publicação: | 2012 |
| País: | España |
| Recursos: | Universitat Politècnica de València (UPV) |
| Repositório: | RiuNet. Repositorio Institucional de la Universitat Politécnica de Valéncia |
| Idioma: | inglês |
| OAI Identifier: | oai:riunet.upv.es:10251/37630 |
| Acesso em linha: | https://riunet.upv.es/handle/10251/37630 |
| Access Level: | Acceso aberto |
| Palavra-chave: | Uncertainty and sensitivity analysis RELAP-PARCS DAKOTA Partial rank correlation coefficient Neutronic parameters Cross sections ESTADISTICA E INVESTIGACION OPERATIVA INGENIERIA NUCLEAR |
| Resumo: | In nuclear safety analysis, it is very important to be able to simulate the different transients that can occur in a nuclear power plant with a very high accuracy. Although the best estimate codes can simulate the transients and provide realistic system responses, the use of nonexactmodels, together with assumptions and estimations, is a source of uncertainties whichmust be properly evaluated. This paper describes a Rod Ejection Accident (REA) simulated using the coupled code RELAP5/PARCSv2.7 with a perturbation on the cross-sectional sets in order to determine the uncertainties in the macroscopic neutronic information. The procedure to performthe uncertainty and sensitivity (U&S) analysis is a sampling-based method which is easy to implement and allows different procedures for the sensitivity analyses despite its high computational time. DAKOTA-Jaguar software package is the selected toolkit for the U&S analysis presented in this paper. The size of the sampling is determined by applying the Wilks¿ formula for double tolerance limits with a 95% of uncertainty and with 95% of statistical confidence for the output variables. Each sample has a corresponding set of perturbations that will modify the cross-sectional sets used by PARCS. Finally, the intervals of tolerance of the output variables will be obtained by the use of nonparametric statistical methods. |
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