Published 2006 | Version v1
Book Metadata-only

Swelling and fission gas release behaviour of mixed carbide fuel of FBTR up to 100 Gwd/T burnup

Creators

  • 1. Post Irradiation, In-service Inspection and Robotics Division, Metallurgy and Materials Group, Indira Gandhi Centre for Atomic Research, Kalpakkam (India)

Description

Mixed carbide fuel (70% PuC with 30% UC) is used as the driver fuel for the Fast Breeder Test Reactor (FBTR) at Kalpakkam. The design burn-up limit and linear heat rating for this fuel was pegged at 50 GWd/t and 320 W/cm due to high swelling rate anticipated for this fuel. Comprehensive analysis of the fuel behaviour such as fuel swelling, fission gas release and microstructure was carried out periodically to consider increase in the linear heat rating and burn-up of this unique fuel. Post Irradiation Examinations (PIE) were carried out on experimental fuel pins irradiated to low burn-up and after a burn up of 25, 50 and 100 Gwd/t

Part of:
Proceedings of the international conference on advances in nuclear materials processing, performance and phenomena and satellite conference on materials behaviour- far from equilibrium: book of abstracts. V.1

Additional details

Publishing Information

Publisher
Bhabha Atomic Research Centre
Imprint Place
Mumbai (India)
Imprint Title
Proceedings of the international conference on advances in nuclear materials processing, performance and phenomena and satellite conference on materials behaviour- far from equilibrium: book of abstracts. V.1
Imprint Pagination
179 p.
Journal Page Range
p. 96

Conference

Title
international conference on advances in nuclear materials processing, performance and phenomena; MBFE 2006: satellite conference on materials behaviour- far from equilibrium
Acronym
ANM 2006
Dates
12-16 Dec 2006
Place
Mumbai (India)

INIS

Country of Publication
India
Country of Input or Organization
India
INIS RN
50063973
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BURNUP; FISSION PRODUCT RELEASE; FUEL-CLADDING INTERACTIONS; KALPAKKAM LMFBR REACTOR; MICROSTRUCTURE; MIXED CARBIDE FUELS; SWELLING
Descriptors DEC
BREEDER REACTORS; DEFORMATION; ENERGY SOURCES; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUELS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS; NUCLEAR FUELS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SOLID FUELS; TEST FACILITIES; TEST REACTORS

Optional Information

Notes
This record replaces 50063193