Reliability assessment of passive containment isolation system using APSRA methodology

被引:10
|
作者
Nayak, A. K. [1 ]
Jain, Vikas [1 ]
Gartia, M. R. [1 ]
Srivastava, A. [2 ]
Prasad, Hari [2 ]
Anthony, A. [1 ]
Gaikwad, A. J. [2 ]
Bhatia, S. [1 ]
Sinha, R. K. [1 ]
机构
[1] Bhabha Atom Res Ctr, Reactor Design Dev Grp, Bombay 400085, Maharashtra, India
[2] Bhabha Atom Res Ctr, Reactor Safety Div, Bombay 400085, Maharashtra, India
关键词
D O I
10.1016/j.anucene.2008.08.011
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
In this paper, a methodology known as APSRA (Assessment of Passive System ReliAbility) has been employed for evaluation of the reliability of passive systems. The methodology has been applied to the passive containment isolation system (PCIS) of the Indian advanced heavy water reactor (AHWR). In the APSRA methodology, the passive system reliability evaluation is based on the failure probability of the system to carryout the desired function. The methodology first determines the operational characteristics of the system and the failure conditions by assigning a predetermined failure criterion. The failure surface is predicted using a best estimate code considering deviations of the operating parameters from their nominal states, which affect the PCIS performance. APSRA proposes to compare the code predictions with the test data to generate the uncertainties on the failure parameter prediction, which is later considered in the code for accurate prediction of failure surface of the system. Once the failure surface of the system is predicted, the cause of failure is examined through root diagnosis, which occurs mainly due to failure of mechanical components. The failure probability of these components is evaluated through a classical PSA treatment using the generic data. The reliability of the PCIS is evaluated from the probability of availability of the components for the success of the passive containment isolation system. (c) 2008 Elsevier Ltd. All rights reserved.
引用
收藏
页码:2270 / 2279
页数:10
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