Open AccessEarly quantification of reliability for a safety critical and control system: a case study of reactor core cooling system
Author(s) -
Vinay Kumar,
Suraj Gupta,
Anil Kumar Tripathi
Publication year - 2018
Publication title -
international journal of engineering and technology
Language(s) - English
Resource type - Journals
ISSN - 2227-524X
DOI - 10.14419/ijet.v7i2.12.11291
Subject(s) - reliability (semiconductor) , reliability engineering , nuclear power plant , nuclear power , nuclear reactor core , probabilistic logic , component (thermodynamics) , nuclear reactor , water cooling , computer science , nuclear engineering , engineering , power (physics) , mechanical engineering , physics , quantum mechanics , artificial intelligence , nuclear physics , thermodynamics
Using Probabilistic Reliability analysis for Quantifying reliability of a system is already a common practice in Reliability Engineering community. This method plays an important role in analyzing reliability of nuclear plants and its various components. In Nuclear Power Plants Reactor Core Cooling System is a component of prime importance as its breakdown can disrupt Cooling System of power plant. In this paper, we present a framework for early quantification of Reliability and illustrated with a Safety Critical and Control System as case study which runs in a Nuclear Power Plant.