Published November 2006 | Version v1
Book

Analysis of grid plate towards remaining life assessment of Fast Breeder Test Reactor

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

Description

Fast Breeder Test Reactor (FBTR) is a loop type reactor with sodium as the primary coolant. Presently FBTR is running with 28 Mark I (70% PuC - 30% UC) fuel subassemblies (FSA), 13 Mark II (55% PuC - 45% UC) FSA and 1 PFBR test FSA. To ease fuel fabrication, it is proposed to use hybrid core (26 Mark I subassemblies in the central core surrounded by 52 MOX subassemblies), which gives 30.7MWt. MOXSA will have 44 wt% of PuO2 and 56 wt% of UO2 with a fissile column length of 430 mm

Part of:
Proceedings of national conference on ageing management of structures, systems and components. V. 2: contributed papers

Additional details

Publishing Information

Publisher
Nuclear Power Corporation of India Ltd.
Imprint Place
Mumbai (India)
ISBN
81-88513-23-7
Imprint Title
Proceedings of national conference on ageing management of structures, systems and components. V. 2: contributed papers
Imprint Pagination
583 p.
Journal Page Range
p. 284-290

Conference

Title
national conference on ageing management of structures, systems and components; NRT - 2: 2. national conference on reactor technology
Acronym
NCAM - 2004
Dates
15-17 Dec 2004
Place
Mumbai (India)

Optional Information

Notes
16 refs., 8 figs.