Published 2012 | Version v1
Book

Fabrication and characterisation of (Th-U) MOX fuel pellets for AHWR-LEU

  • 1. Radiometallurgy Division, Nuclear Fuels Group, Bhabha Atomic Research Centre, Mumbai (India)

Description

The Advanced Heavy Water Reactor (AHWR-LEU) is a 300 MWe, vertical, pressure tube type, boiling light water cooled, and heavy water moderated reactor. The reactor will use (Thorium-LEU) MOX as fuel with LEU (Low Enriched Uranium) having 235U enrichment of 19.75 %. The fuel cluster of AHWR-300 LEU has 54 zircaloy-2 clad fuel pins containing sintered (Th,U)O2 pellets arranged in three concentric rings. The LEU content in the (Thorium-LEU) MOX is different for the different rings of fuel pins in the cluster. In the present investigation, pellets of ThO2 containing 8, 10, 12, 15, 18, 20 and 22.5 wt % natural UO2 were fabricated by conventional powder pellet route. Detailed fabrication parameters like compaction pressure, sintering temperature, atmosphere, effects of dopants etc. were studied

Part of:
Proceedings of the international conference on characterization and quality control of nuclear fuels: inaugural and technical sessions and abstracts

Additional details

Publishing Information

Publisher
Nuclear Fuel Complex
Imprint Place
Hyderabad (India)
Imprint Title
Proceedings of the international conference on characterization and quality control of nuclear fuels: inaugural and technical sessions and abstracts
Imprint Pagination
181 p.
Journal Page Range
p. 112-113

Conference

Title
4. international conference on characterization and quality control of nuclear fuels
Acronym
CQCNF-2012
Dates
27-29 Feb 2012
Place
Hyderabad (India)

Optional Information

Notes
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