Probabilistic methods in nuclear power plant component ageing analysis

Kaisa Simola

Research output: Book/ReportReportProfessional

Abstract

The nuclear power plant ageing research is aimed to ensure that the plant safety and reliability are maintained at a desired level through the designed, and possibly extended, lifetime. In ageing studies, the reliability of components, systems and structures is evaluated taking into account the possible time dependent decrease in reliability. The results of analyses can be used in the evaluation of the remaining lifetime of components and in the development of preventive maintenance, testing and replacement programmes. This report discusses the use of probabilistic models in the evaluation of the ageing of nuclear power plant components. The principles of nuclear power plant ageing studies are described and examples of ageing management programmes in foreign countries are given. The use of time dependent probabilistic models to evaluate the ageing of various components and structures is described and the application of models is demonstrated with two case studies. In the case study of motor operated closing valves the analyses are based on failure data obtained from a power plant. In me second example, the environmentally assisted crack growth is modelled with a computer code developed in United States, and the applicability of the model is evaluated on the basis of operating experience.
Original languageEnglish
Place of PublicationEspoo
PublisherVTT Technical Research Centre of Finland
Number of pages87
ISBN (Print)951-38-4072-7
Publication statusPublished - 1992
MoE publication typeNot Eligible

Publication series

NameVTT publications
PublisherVTT
No.94
ISSN (Print)1235-0621
ISSN (Electronic)1455-0849

Fingerprint

Nuclear power plants
Aging of materials
Preventive maintenance
Plant shutdowns
Crack propagation
Power plants
Testing
Statistical Models

Keywords

  • nuclear power plants
  • service life
  • nuclear reactor safety
  • safety
  • reliability
  • components
  • probability theory
  • statistical analysis
  • mathematical prediction
  • valves
  • crack propagation

Cite this

Simola, K. (1992). Probabilistic methods in nuclear power plant component ageing analysis. Espoo: VTT Technical Research Centre of Finland. VTT Publications, No. 94
Simola, Kaisa. / Probabilistic methods in nuclear power plant component ageing analysis. Espoo : VTT Technical Research Centre of Finland, 1992. 87 p. (VTT Publications; No. 94).
@book{88a303d626074e29b7b82d423840e3c1,
title = "Probabilistic methods in nuclear power plant component ageing analysis",
abstract = "The nuclear power plant ageing research is aimed to ensure that the plant safety and reliability are maintained at a desired level through the designed, and possibly extended, lifetime. In ageing studies, the reliability of components, systems and structures is evaluated taking into account the possible time dependent decrease in reliability. The results of analyses can be used in the evaluation of the remaining lifetime of components and in the development of preventive maintenance, testing and replacement programmes. This report discusses the use of probabilistic models in the evaluation of the ageing of nuclear power plant components. The principles of nuclear power plant ageing studies are described and examples of ageing management programmes in foreign countries are given. The use of time dependent probabilistic models to evaluate the ageing of various components and structures is described and the application of models is demonstrated with two case studies. In the case study of motor operated closing valves the analyses are based on failure data obtained from a power plant. In me second example, the environmentally assisted crack growth is modelled with a computer code developed in United States, and the applicability of the model is evaluated on the basis of operating experience.",
keywords = "nuclear power plants, service life, nuclear reactor safety, safety, reliability, components, probability theory, statistical analysis, mathematical prediction, valves, crack propagation",
author = "Kaisa Simola",
note = "Project code: S{\"A}H01271",
year = "1992",
language = "English",
isbn = "951-38-4072-7",
series = "VTT publications",
publisher = "VTT Technical Research Centre of Finland",
number = "94",
address = "Finland",

}

Simola, K 1992, Probabilistic methods in nuclear power plant component ageing analysis. VTT Publications, no. 94, VTT Technical Research Centre of Finland, Espoo.

Probabilistic methods in nuclear power plant component ageing analysis. / Simola, Kaisa.

Espoo : VTT Technical Research Centre of Finland, 1992. 87 p. (VTT Publications; No. 94).

Research output: Book/ReportReportProfessional

TY - BOOK

T1 - Probabilistic methods in nuclear power plant component ageing analysis

AU - Simola, Kaisa

N1 - Project code: SÄH01271

PY - 1992

Y1 - 1992

N2 - The nuclear power plant ageing research is aimed to ensure that the plant safety and reliability are maintained at a desired level through the designed, and possibly extended, lifetime. In ageing studies, the reliability of components, systems and structures is evaluated taking into account the possible time dependent decrease in reliability. The results of analyses can be used in the evaluation of the remaining lifetime of components and in the development of preventive maintenance, testing and replacement programmes. This report discusses the use of probabilistic models in the evaluation of the ageing of nuclear power plant components. The principles of nuclear power plant ageing studies are described and examples of ageing management programmes in foreign countries are given. The use of time dependent probabilistic models to evaluate the ageing of various components and structures is described and the application of models is demonstrated with two case studies. In the case study of motor operated closing valves the analyses are based on failure data obtained from a power plant. In me second example, the environmentally assisted crack growth is modelled with a computer code developed in United States, and the applicability of the model is evaluated on the basis of operating experience.

AB - The nuclear power plant ageing research is aimed to ensure that the plant safety and reliability are maintained at a desired level through the designed, and possibly extended, lifetime. In ageing studies, the reliability of components, systems and structures is evaluated taking into account the possible time dependent decrease in reliability. The results of analyses can be used in the evaluation of the remaining lifetime of components and in the development of preventive maintenance, testing and replacement programmes. This report discusses the use of probabilistic models in the evaluation of the ageing of nuclear power plant components. The principles of nuclear power plant ageing studies are described and examples of ageing management programmes in foreign countries are given. The use of time dependent probabilistic models to evaluate the ageing of various components and structures is described and the application of models is demonstrated with two case studies. In the case study of motor operated closing valves the analyses are based on failure data obtained from a power plant. In me second example, the environmentally assisted crack growth is modelled with a computer code developed in United States, and the applicability of the model is evaluated on the basis of operating experience.

KW - nuclear power plants

KW - service life

KW - nuclear reactor safety

KW - safety

KW - reliability

KW - components

KW - probability theory

KW - statistical analysis

KW - mathematical prediction

KW - valves

KW - crack propagation

M3 - Report

SN - 951-38-4072-7

T3 - VTT publications

BT - Probabilistic methods in nuclear power plant component ageing analysis

PB - VTT Technical Research Centre of Finland

CY - Espoo

ER -

Simola K. Probabilistic methods in nuclear power plant component ageing analysis. Espoo: VTT Technical Research Centre of Finland, 1992. 87 p. (VTT Publications; No. 94).