Published 2000 | Version v1
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MOX fuel for Indian nuclear power programme

  • 1. Bhabha Atomic Research Centre, Trombay, Mumbai (India)

Description

A sound energy policy and a sound environmental policy calls for utilisation of plutonium (Pu) in nuclear power reactors. The paper discusses the use of Pu in the form of mixed oxide (MOX) fuel in two Indian boiling water reactors (BWRs) at Tarapur. An industrial scale MOX fuel fabrication plant is presently operational at Tarapur which is capable of manufacturing MOX fuels for BWRs and in future for PHWRs. The plant can also manufacture mixed oxide fuel for prototype fast breeder reactor (PFBR) and development work in this regard has already started. The paper describes the MOX fuel manufacturing technology and quality control techniques presently in use at the plant. The irradiation experience of the lead MOX assemblies in BWRs is also briefly discussed. The key areas of interest for future developments in MOX fuel fabrication technology and Pu utilisation are identified. (author)

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Part of:
MOX fuel cycle technologies for medium and long term deployment. Proceedings

Additional details

Publishing Information

Imprint Title
MOX fuel cycle technologies for medium and long term deployment. Proceedings
Imprint Pagination
556 p.
Journal Issue
no. 3/P
Series
C and S papers series
Journal Page Range
p. 190-199
ISSN
1563-0153
Report number
IAEA-CSP--3/P

Conference

Title
International symposium on MOX fuel cycle technologies for medium and long term deployment
Dates
17-21 May 1999
Place
Vienna (Austria)

Optional Information

Notes
21 refs, 3 figs, 5 tabs
Secondary number(s)
IAEA-SM--358/13