Reliability assessment of the passive heat removal system of the VVER-1000 reactor at Kudankulam NPP
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P. Khubchandani
Abstract
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.
Kurzfassung
Zur Analyse der Fehleranfälligkeit des Systems wurde ein Modell entwickelt auf der Grundlage des Best Estimate T–H code RELAP5/Mod3.3. Die Parameter, die die Leistungsfähigkeit des Systems beeinflussen, wurden identifiziert und ihre Reichweite und Verteilung wurde bestimmt. Die Durchführbarkeit verschiedener Methoden zu Berechnung der funktionalen Zuverlässigkeit wurde analysiert und die Response-Surface-Methode wurde ausgewählt. Eine Antwortfläche wurde mit Hilfe der Monte-Carlo-Methode für den gesamten Parameterbereich konstruiert. Eine große Anzahl von Inputparametern wurde erzeugt, unter Berücksichtigung ihrer individuellen Verteilungen. Sie wurden als Erfolg/Misserfolg klassifiziert je nach ihrer Position in Bezug auf die Fehlerfläche. Das Verhältnis zwischen erfolgreichen Proben und Fehlerproben ergibt die Fehlerwahrscheinlichkeit. Es wurde versucht, die funktionale Fehlerwahrscheinlichkeit in die Komponentenfehlerwahrscheinlichkeit des Systems zu integrieren, um so die Gesamtfehlerwahrscheinlichkeit des Systems zu erhalten.
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Development of inflatable seals for the rotatable plugs of sodium cooled fast breeder reactors: a review – Part II: R&D necessities and development across the world
- Analysis of radwaste management alternatives during dismantling of Ignalina NPP systems with low level contamination
- Calculation of excitation functions for the production of Cu and Co medical isotopes
- Reliability assessment of the passive heat removal system of the VVER-1000 reactor at Kudankulam NPP
- Calculation of the neutronic behavior of minor actinides burning in a thermal research reactor using the MCNPX 2.6 code
- Steam drum level control studies of a natural circulation multi loop reactor
- Analyses in regulatory practice
- Technical Notes/Technische Mitteilungen
- Installation and measurement capacity of 3 × 592 GBq 241Am–Be neutron irradiation cell
- Calculation of the critical thickness for one-speed neutrons in a reflected slab with backward and forward scattering using modified TN method
