Probabilistic ageing and risk analysis tools for nuclear piping
- 1. Paul Scherrer Institute (PSI), Nuclear Energy and Safety Department, Laboratory for Nuclear Materials, OHSA/B06, 5232 Villigen (Switzerland)
- 2. Institute of Nuclear Energy Research, Taoyuan 32546, Taiwan (China)
Description
Probabilistic fracture mechanics (PFM) is used to demonstrate the safety of nuclear power plant (NPP) components. With PFM, fracture mechanics methods and reliability theory are combined for assessing the reliability of cracked components. This paper describes PFM calculations for the leak-before-break (LBB) of piping using the pc-PRAISE and PRO-LOCA computer codes. The procedure, methods and computer codes for probabilistic piping assessment are briefly reviewed and compared. The codes consider the failure mechanisms of stress corrosion cracking (SCC) and fatigue for piping and operating conditions that are susceptible to cracking. Two benchmark cases are used to demonstrate the applicability of the computer codes and probabilistic methods in nuclear piping. Sensitivity calculations show that the predicted failure probabilities are sensitive to the operating pressure and temperature, in-service inspection interval and welding residual stress.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2016.02.033Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2016.02.033;
- PII
- S0029-5493(16)00095-9;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 300
- Journal Page Range
- p. 541-551
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48005679
- Subject category
- S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- COMPARATIVE EVALUATIONS; COMPUTER CODES; CRACKING; CRACKS; FATIGUE; FRACTURE MECHANICS; FRACTURES; IN-SERVICE INSPECTION; LOSS OF COOLANT; NUCLEAR POWER PLANTS; PROBABILISTIC ESTIMATION; REACTOR SAFETY; RELIABILITY; RESIDUAL STRESSES; RISK ASSESSMENT; SAFETY ANALYSIS; STRESS CORROSION; WELDING
- Descriptors DEC
- ACCIDENTS; CALCULATION METHODS; CHEMICAL REACTIONS; CORROSION; DECOMPOSITION; EVALUATION; FABRICATION; FAILURES; INSPECTION; JOINING; MECHANICAL PROPERTIES; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; PYROLYSIS; REACTOR ACCIDENTS; SAFETY; STRESSES; THERMAL POWER PLANTS; THERMOCHEMICAL PROCESSES
Optional Information
- Copyright
- Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.