Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: Experience of thorium fuel development in India

Majumdar, S.; Purushotham, D.S.C. (Bhabha Atomic Research Centre, Mumbai (India))

Abstract

India has one of the largest resources of thorium in the beach sands of Southern India. Generation of nuclear power through utilization of thorium is the ultimate goal of India's three stage nuclear power strategy. Bhabha Atomic Research Centre (BARC) is actively pursuing research, development, fabrication, characterization and irradiating testing of ThO2, ThO2-PuO2, ThO2-UO2 fuels in test and power reactors. Work related to developing the fuel fabrication technology including automation and remotization needed for 233U based fuels is in progress. Use of ThO2 fuel bundles for initial flux flattening in our PHWRs. Recent criticality of KAMINI - a small neutron source reactor, with 233U-Al alloy fuel. Introduction of ThO2 as axial and radial blankets in our Fast Breeder Test Reactor (FBTR) at Kalpakkam. Proposed ThO2-PuO2 and ThO2-233UO2 fuel for Advanced Heavy Water Reactor (AHWR) are some of the steps taken by us towards utilization of Thorium in India. The paper summarizes the present status of thorium fuel development in India.

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key words: breeding blankets; energy policy; fuel pellets; india; kalpakkam lmfbr reactor; mixed oxide fuels; phwr type reactors; sintering; thorium cycle; thorium oxides; thorium reserves
Reference:
Proceedings of three IAEA meetings held in Vienna in 1997, 1998 and 1999
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--1319, pp:69-76