Published 2015 | Version v1
Book

Reliability analysis of SGDHR dampers

  • 1. Reactor Design Group, Indira Gandhi Centre for Atomic Research, Kalpakkam (India)

Description

Prototype Fast Breeder Reactor (PFBR) is a 500 MWe, sodium cooled, mixed oxide fuelled, pool type fast reactor being constructed at Kalpakkam, India. PFBR has two independent and diverse Decay Heat Removal (DHR) systems viz., Operating Grade Decay Heat Removal System (OGDHRS) and Safety Grade Decay Heat Removal System (SGDHRS). The present work reports the reliability analysis of the dampers of the SGDHR system. The relay logic, actuators, valves, power supply and mechanical part of dampers are modeled for both the electrical and pneumatic dampers of SGDHRS. This work includes the results of two cases viz., i) Failure probability of each of the dampers to assess the performance of individual electrical and pneumatic damper in a loop, and ii) Failure probability of SGDHR dampers in a single loop. The second case includes common cause failures of motors, class II system, valves and relays. Uncertainty analysis and sensitivity studies have also been carried out for both electric and pneumatic dampers

Part of:
Proceedings of the international workshops on NPPs-safety and sustainability and new horizons in nuclear reactor thermal-hydraulics and safety

Additional details

Publishing Information

Publisher
Atomic Energy Regulatory Board
Imprint Place
Mumbai (India)
Imprint Title
Proceedings of the international workshops on NPPs-safety and sustainability and new horizons in nuclear reactor thermal-hydraulics and safety
Imprint Pagination
769 p.
Journal Page Range
8 p.

Conference

Title
international workshop on NPPs-safety and sustainability; NHNRTHS-2015: international workshop on new horizons in nuclear reactor thermal-hydraulics and safety
Acronym
CANSAS-2015
Dates
8-11 Dec 2015
Place
Mumbai (India)

Optional Information

Notes
11 refs., 7 figs., 4 tabs.