Published July 1981 | Version v1
Report

Analysis of taps fuel performance data to examine the feasibility of extended discharge burnup

  • 1. Bhabha Atomic Research Centre, Bombay (India). Radiometallurgy Section

Description

Under a programme to assess the performance of fuel elements of Tarapur Atomic Power Station (TAPS) the available data on fuel failure collected during in-core sipping, non-destructive testing at the pool site and post-irradiation examination in hot cells at Trombay have been analysed. The following aspects of fuel performance have been studied: (i) Fuel failure pattern in the core using the cumulative distribution of leakers in the core till the end of sixth cycle. (ii) Fuel failure pattern in the assembly by assessing fuel failure data generated during non-destructive testing of more than 3,000 fuel elements of initial load design. (iii) Burnup dependence of fuel failure by correlating the assembly average burnup with the number of leakers. (iv) Fuel failure mode and other aspects of fuel performance have been studied by detailed hot cell examination of 18 fuel elements of varying burnup in the range 6,000 to 29,000 MWD/MTU. The present paper briefly reviews the current understanding of TAPS fuel performance and the feasibility of extending the fuel discharge burnup. (author)

Additional details

Publishing Information

Imprint Title
Specialists' meeting on high burnup in power reactors fuel. CEN/SCK - Mol, Belgium, 24-27 March 1981
Imprint Pagination
132 p.
Journal Page Range
p. 47-51.
Report number
IWGFPT--10

Conference

Title
Specialists' meeting on high burnup in power reactors fuel.
Dates
24 - 27 Mar 1981.
Place
Mol, Belgium.

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
12638870
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BURNUP; FEASIBILITY STUDIES; FUEL ELEMENT FAILURE; FUEL ELEMENTS; FUEL MANAGEMENT; HOT CELLS; LEAKS; NONDESTRUCTIVE TESTING; TARAPUR-1 REACTOR
Descriptors DEC
ACCIDENTS; BWR TYPE REACTORS; ENRICHED URANIUM REACTORS; LABORATORY EQUIPMENT; MANAGEMENT; MATERIALS TESTING; NUCLEAR MATERIALS MANAGEMENT; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS