Statistical analysis of fuel failures in large break loss-of-coolant accident (LBLOCA) in EPR type nuclear power plant

Asko Arkoma (Corresponding Author), Markku Hänninen, Karin Rantamäki, Joona Kurki, Anitta Hämäläinen

Research output: Contribution to journalArticleScientificpeer-review

11 Citations (Scopus)

Abstract

In this paper, the number of failing fuel rods in a large break loss-of-coolant accident (LB-LOCA) in EPR-type nuclear power plant is evaluated using statistical methods. For this purpose, a statistical fuel failure analysis procedure has been developed. The developed method utilizes the results of nonparametric statistics, the Wilks' formula in particular, and is based on the selection and variation of parameters that are important in accident conditions. The accident scenario is simulated with the coupled fuel performance - thermal hydraulics code FRAPTRAN-GENFLO using various parameter values and thermal hydraulic and power history boundary conditions between the simulations. The number of global scenarios is 59 (given by the Wilks' formula), and 1000 rods are simulated in each scenario. The boundary conditions are obtained from a new statistical version of the system code APROS. As a result, in the worst global scenario, 1.2% of the simulated rods failed, and it can be concluded that the Finnish safety regulations are hereby met (max. 10% of the rods allowed to fail).
Original languageEnglish
Pages (from-to)1-14
JournalNuclear Engineering and Design
Volume285
DOIs
Publication statusPublished - 2015
MoE publication typeA1 Journal article-refereed

Fingerprint

loss of coolant
Loss of coolant accidents
nuclear power plants
electron spin resonance
accidents
nuclear power plant
statistical analysis
Nuclear power plants
accident
Paramagnetic resonance
Statistical methods
rods
Accidents
boundary condition
Hydraulics
Boundary conditions
hydraulics
nonparametric statistics
failure analysis
boundary conditions

Keywords

  • loss-of-coolant accident
  • EPR
  • Wilks' formula
  • FRAPTRAN-GENFLO
  • APROS
  • statistical fuel failure analysis

Cite this

@article{7970032b9284495586b5b3dc2c07590b,
title = "Statistical analysis of fuel failures in large break loss-of-coolant accident (LBLOCA) in EPR type nuclear power plant",
abstract = "In this paper, the number of failing fuel rods in a large break loss-of-coolant accident (LB-LOCA) in EPR-type nuclear power plant is evaluated using statistical methods. For this purpose, a statistical fuel failure analysis procedure has been developed. The developed method utilizes the results of nonparametric statistics, the Wilks' formula in particular, and is based on the selection and variation of parameters that are important in accident conditions. The accident scenario is simulated with the coupled fuel performance - thermal hydraulics code FRAPTRAN-GENFLO using various parameter values and thermal hydraulic and power history boundary conditions between the simulations. The number of global scenarios is 59 (given by the Wilks' formula), and 1000 rods are simulated in each scenario. The boundary conditions are obtained from a new statistical version of the system code APROS. As a result, in the worst global scenario, 1.2{\%} of the simulated rods failed, and it can be concluded that the Finnish safety regulations are hereby met (max. 10{\%} of the rods allowed to fail).",
keywords = "loss-of-coolant accident, EPR, Wilks' formula, FRAPTRAN-GENFLO, APROS, statistical fuel failure analysis",
author = "Asko Arkoma and Markku H{\"a}nninen and Karin Rantam{\"a}ki and Joona Kurki and Anitta H{\"a}m{\"a}l{\"a}inen",
note = "Project code: 83897",
year = "2015",
doi = "10.1016/j.nucengdes.2014.12.023",
language = "English",
volume = "285",
pages = "1--14",
journal = "Nuclear Engineering and Design",
issn = "0029-5493",
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}

Statistical analysis of fuel failures in large break loss-of-coolant accident (LBLOCA) in EPR type nuclear power plant. / Arkoma, Asko (Corresponding Author); Hänninen, Markku; Rantamäki, Karin; Kurki, Joona; Hämäläinen, Anitta.

In: Nuclear Engineering and Design, Vol. 285, 2015, p. 1-14.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Statistical analysis of fuel failures in large break loss-of-coolant accident (LBLOCA) in EPR type nuclear power plant

AU - Arkoma, Asko

AU - Hänninen, Markku

AU - Rantamäki, Karin

AU - Kurki, Joona

AU - Hämäläinen, Anitta

N1 - Project code: 83897

PY - 2015

Y1 - 2015

N2 - In this paper, the number of failing fuel rods in a large break loss-of-coolant accident (LB-LOCA) in EPR-type nuclear power plant is evaluated using statistical methods. For this purpose, a statistical fuel failure analysis procedure has been developed. The developed method utilizes the results of nonparametric statistics, the Wilks' formula in particular, and is based on the selection and variation of parameters that are important in accident conditions. The accident scenario is simulated with the coupled fuel performance - thermal hydraulics code FRAPTRAN-GENFLO using various parameter values and thermal hydraulic and power history boundary conditions between the simulations. The number of global scenarios is 59 (given by the Wilks' formula), and 1000 rods are simulated in each scenario. The boundary conditions are obtained from a new statistical version of the system code APROS. As a result, in the worst global scenario, 1.2% of the simulated rods failed, and it can be concluded that the Finnish safety regulations are hereby met (max. 10% of the rods allowed to fail).

AB - In this paper, the number of failing fuel rods in a large break loss-of-coolant accident (LB-LOCA) in EPR-type nuclear power plant is evaluated using statistical methods. For this purpose, a statistical fuel failure analysis procedure has been developed. The developed method utilizes the results of nonparametric statistics, the Wilks' formula in particular, and is based on the selection and variation of parameters that are important in accident conditions. The accident scenario is simulated with the coupled fuel performance - thermal hydraulics code FRAPTRAN-GENFLO using various parameter values and thermal hydraulic and power history boundary conditions between the simulations. The number of global scenarios is 59 (given by the Wilks' formula), and 1000 rods are simulated in each scenario. The boundary conditions are obtained from a new statistical version of the system code APROS. As a result, in the worst global scenario, 1.2% of the simulated rods failed, and it can be concluded that the Finnish safety regulations are hereby met (max. 10% of the rods allowed to fail).

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