Published 2014 | Version v1
Book

Post Fukushima safety assessment of FBTR - salient observations, strategies and retrofits

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

Description

Fast Breeder Test Reactor (FBTR) is India's first liquid metal cooled fast reactor (LMFBR). FBTR uses mixed carbide of U and Pu as driver fuel and rated for a nominal power of 40 MWt. Heat transport system comprises two sodium coolant loops with pumps and intermediate heat exchangers (IHX). A turbo alternator with associated steam plant for generating about 13 MW electrical power. The main issues of safety assessment were the effects and implications of the revised flood level, including the effect of extended station black out on reactor safety. Summary of review, recommendations and action plan for ensuring safe shutdown followed by DHR and containment integrity is given in this paper. (author)

Part of:
Proceedings of the international workshop on new horizons in nuclear reactor thermal hydraulics and safety

Additional details

Publishing Information

Publisher
Bhabha Atomic Research Centre
Imprint Place
Mumbai (India)
Imprint Title
Proceedings of the international workshop on new horizons in nuclear reactor thermal hydraulics and safety
Imprint Pagination
91 p.
Journal Page Range
[4 p.]

Conference

Title
international workshop on new horizons in nuclear reactor thermal hydraulics and safety
Acronym
IW-NRTHS 2014
Dates
13-15 Jan 2014
Place
Mumbai (India)

Optional Information

Notes
2 refs., 4 figs.