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