Published 2001 | Version v1
Book

Studies on the dissolution characteristics of sintered thoria (ThO2) - 4% PuO2 pellet

  • 1. Process Development Division, Bhabha Atomic Research Centre, Mumbai (India)

Description

India's nuclear power programme is expected to use our vast deposits of thorium in its third and final phase. Zircaloy clad thoria in combination with 233UO2 and PuO2 will be the fuel, in an advanced heavy water reactor being setup at BARC which will be a forerunner for the transfer to thorium based systems. This paper describes the preliminary studies carried out on the dissolution characteristics of sintered thoria-4% PuO2 pellet with 94% TD, which is one of the typical fuel configurations. (author)

Part of:
Proceedings of BRNS-DAE national symposium on nuclear and radiochemistry

Additional details

Publishing Information

Publisher
Bhabha Atomic Research Centre
Imprint Place
Mumbai (India)
Imprint Title
Proceedings of BRNS-DAE national symposium on nuclear and radiochemistry
Imprint Pagination
587 p.
Journal Page Range
p. 210-211

Conference

Title
5. national symposium on nuclear and radiochemistry
Acronym
NUCAR 2001
Dates
7-10 Feb 2001
Place
Pune (India)

Optional Information

Notes
2 refs., 1 fig.