Reliability assessment of passive isolation condenser system of AHWR using APSRA methodology
Creators
- 1. Reactor Design Development Group, Bhabha Atomic Research Centre, Trombay, Mumbai 400085 (India)
- 2. Reactor Safety Division, Bhabha Atomic Research Centre, Trombay, Mumbai 400085 (India)
Description
In this paper, a methodology known as APSRA (Assessment of Passive System ReliAbility) is used for evaluation of reliability of passive isolation condenser system of the Indian Advanced Heavy Water Reactor (AHWR). As per the APSRA methodology, the passive system reliability evaluation is based on the failure probability of the system to perform the design basis function. The methodology first determines the operational characteristics of the system and the failure conditions based on a predetermined failure criterion. The parameters that could degrade the system performance are identified and considered for analysis. Different modes of failure and their cause are identified. The failure surface is predicted using a best estimate code considering deviations of the operating parameters from their nominal states, which affect the isolation condenser system performance. Once the failure surface of the system is predicted, the causes of failure are examined through root diagnosis, which occur mainly due to failure of mechanical components. Reliability of the system is evaluated through a classical PSA treatment based on the failure probability of the components using generic data
Availability note (English)
Available from http://dx.doi.org/10.1016/j.ress.2008.12.002Additional details
Identifiers
- DOI
- 10.1016/j.ress.2008.12.002;
- PII
- S0951-8320(08)00290-1;
Publishing Information
- Journal Title
- Reliability Engineering and System Safety
- Journal Volume
- 94
- Journal Issue
- 6
- Journal Page Range
- p. 1064-1075
- ISSN
- 0951-8320
- CODEN
- RESSEP
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 40045959
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- EVALUATION; FAILURES; HEAVY WATER COOLED REACTORS; ISOLATION CONDENSERS; PERFORMANCE; PROBABILITY; REACTOR SAFETY; RELIABILITY
- Descriptors DEC
- REACTORS; SAFETY; STEAM CONDENSERS; VAPOR CONDENSERS
Optional Information
- Copyright
- Copyright (c) 2008 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.