Insights from level-1 Probabilistic Safety Analysis of Prototype Fast Breeder Reactor

被引：4

作者：

Ramakrishnan, M. ^{[1
]}

Sharma, Pramod Kumar ^{[1
]}

Bhuvana, V ^{[1
]}

Arul, John A. ^{[1
]}

Mohanakrishnan, P. ^{[1
]}

Chetal, S. C.

机构：

[1] Indira Gandhi Ctr Atom Res IGCAR, Reactor Phys Grp RPhG, Kalpakkam 603102, Tamil Nadu, India

来源：

NUCLEAR ENGINEERING AND DESIGN | 2012年 / 250卷

关键词：

D O I：

10.1016/j.nucengdes.2012.05.006

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：

This paper presents the results and important insights from level-1 Probabilistic Safety Analysis of Prototype Fast Breeder Reactor (PFBR) which is under construction at Kalpakkam. Level-1 PSA of PFBR was carried out as per the regulatory requirement in India. The desired target value for overall Core Damage Frequency (CDF) of PFBR is <= 1 E-6/reactor year (ry). The scope of this study is limited to internal events at full power. The salient feature of this study is the inclusion of functional failure of natural convection based decay Heat Removal System in event tree development. As in most of the safety systems the unavailability contribution is dominated by CCF events and hence are highly sensitive to CCF model parameters. The dominant contributors to Core Damage Frequency are Loss of Off-Site Power and Loss of Steam Water System. Research & Development (R&D) input is required in modeling flow blockage events which has the largest uncertainty. (C) 2012 Elsevier B.V. All rights reserved.

引用

页码：664 / 670

页数：7

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