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Citation
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HERO ID
1440652
Reference Type
Journal Article
Title
Fast reactor fuel reprocessing technology in India
Author(s)
Natarajan, R; Raj, B
Year
2007
Is Peer Reviewed?
Yes
Journal
Journal of Nuclear Science and Technology
ISSN:
0022-3131
Volume
44
Issue
3
Page Numbers
393-397
Web of Science Id
WOS:000246292000022
Abstract
The limited indigenous uranium resource coupled with the
need of energy independence necessitated the Department of Atomic Energy (DAE) in India to opt
for a three-stage nuclear power program comprising of PHWRs in Stage 1, FBRs in Stage 2 and Th-
U-233 based reactors in Stage 3, respectively to meet the energy needs of the growing Indian
economy. Presently the country has stepped into the 2nd Stage. The transition from the Stage 1 to
2 was fruitful thanks to the 2-decade long R&D experience gained in Fast Reactor Fuel
Reprocessing (FRFR). Closing the fast reactor fuel cycle through FRFR was inevitable for the
success of the Indian Nuclear Power Program (INPP). The latest achievement by the center was the
successful reprocessing of 100GWd/t burnup mixed carbide fuel with 70% Pu, discharged from the
Fast Breeder Test Reactor (FBTR) which is also located in the same center. The designs of the
various equipments and process flow sheet had stemmed from the above experiences thereby
increasing the confidence level in the future plans of the Department. In this paper, an overview
of the experiences in FRFR with glimpses of the various developmental activities towards the
future plants is spelt out.
Keywords
fast reactor; fast reactor fuel reprocessing; single pin chopper; centrifugal extractor; SIMPSEX
Tags
IRIS
•
Uranium
WOS
Merged reference set
Secondary Refinement
Excluded
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