Reliability assessment of the passive heat removal system of the VVER-1000 reactor at Kudankulam NPP
- 1. Nuclear Power Corporation of India Ltd, Kudankulam (India)
- 2. Bhabha Atomic Research Centre, Trombay, Mumbai (India)
Description
For analyzing the failure probability of the system, a model of the system was developed in best estimate T-H code RELAP5/Mod3.3. The parameters affecting the system performance were identified, their range and distribution was determined. Feasibility of various methods for calculating functional reliability was analyzed. The response surface method was selected. A response surface was constructed for the entire range of parameters for the model developed using Monte Carlo method. A large number of samples of the input parameters was generated, taking into account their individual distributions. They were classified as success/failure based on their position with respect to the failure surface. The ratio of the failed samples to the successful samples gives us the failure probability. An attempt was also made to integrate the functional failure probability with the component failure probability of the system to get an overall failure probability of the system. (orig.)
Additional details
Publishing Information
- Journal Title
- Kerntechnik (1987)
- Journal Volume
- 78
- Journal Issue
- 6
- Journal Page Range
- p. 489-495
- ISSN
- 0932-3902
- CODEN
- KERNEU
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 45021719
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- FAILURES; HEAT EXCHANGERS; KUDANKULAM-1 REACTOR; KUDANKULAM-2 REACTOR; LOSS OF COOLANT; MONTE CARLO METHOD; NUCLEAR POWER PLANTS; PERFORMANCE; PROBABILITY; R CODES; REACTOR COOLING SYSTEMS; RELIABILITY; VALIDATION
- Descriptors DEC
- ACCIDENTS; CALCULATION METHODS; COMPUTER CODES; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; TESTING; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS