Condition-based probabilistic safety assessment for maintenance decision making regarding a nuclear power plant steam generator undergoing multiple degradation mechanisms
- 1. Energy Department, Politecnico di Milano, Via La Masa 34, 20156 Milano (Italy)
- 2. Eminent Scholar, Department of Nuclear Engineering, Kyung Hee University (Korea, Republic of)
- 3. MINES ParisTech / PSL Université Paris, Centre de Recherche sur les Risques et les Crises (CRC), Sophia Antipolis (France)
Description
Highlights: • CB-PSA systematically integrates condition monitoring in the framework of PSA. • CB-PSA allows living risk prioritization that impacts the lifecycle asset management. • Maintenance decisions are taken for a SG undergoing multiple degradation mechanisms. • Decisions taken by CB-PSA significantly reduces SGTR risk and maintenance cost. -- Abstract: Condition-Based Probabilistic Safety Assessment (CB-PSA) makes use of inspections and monitoring information on Systems, Structures, and Components (SSCs) to update risk quantities. In this paper, we show the benefits of exploiting the condition-based estimates for taking maintenance decisions on a SSC undergoing multiple degradation mechanisms. To develop the method, we make reference to a spontaneous Steam Generator Tube Rupture (SGTR) Accident Scenario in a Nuclear Power Plant (NPP). The SG is susceptible to multiple degradation mechanisms, i.e., Stress Corrosion Cracking (SCC) and pitting. Tube plugging and Water Lancing and Chemical Cleaning (WL-CC) can be performed, before leading to a SGTR accident. Decisions must be taken on the maintenance strategy to perform at each inspection cycle. Results of a case study regarding SGTR show that the decisions based on the risk estimates provided by a CB-PSA approach allow controlling the SGTR risk at minimum maintenance cost.
Additional details
Identifiers
- DOI
- 10.1016/j.ress.2019.106583;
- PII
- S0951832018310767;
Publishing Information
- Journal Title
- Reliability Engineering and System Safety
- Journal Volume
- 191
- Journal Page Range
- vp.
- ISSN
- 0951-8320
- CODEN
- RESSEP
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 55017144
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING;
- Descriptors DEI
- CRACKING; NUCLEAR POWER PLANTS; PROBABILISTIC ESTIMATION; PROGRAM MANAGEMENT; REACTOR MAINTENANCE; RISK ASSESSMENT; STEAM GENERATOR TUBE RUPTURE; STEAM GENERATORS; STRESS CORROSION
- Descriptors DEC
- ACCIDENTS; BOILERS; CALCULATION METHODS; CHEMICAL REACTIONS; CORROSION; DECOMPOSITION; MAINTENANCE; MANAGEMENT; NUCLEAR FACILITIES; OPERATION; POWER PLANTS; PYROLYSIS; REACTOR ACCIDENTS; REACTOR LIFE CYCLE; REACTOR OPERATION; THERMAL POWER PLANTS; THERMOCHEMICAL PROCESSES; VAPOR GENERATORS
Optional Information
- Copyright
- Copyright (c) 2019 Elsevier Ltd. All rights reserved.