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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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)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 31062341
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; FBR TYPE REACTORS; INDIA; MIXED OXIDE FUEL FABRICATION PLANTS; MIXED OXIDE FUELS; PHWR TYPE REACTORS; QUALITY CONTROL; TECHNOLOGY ASSESSMENT
- Descriptors DEC
- ASIA; BREEDER REACTORS; CONTROL; DEVELOPING COUNTRIES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FUEL FABRICATION PLANTS; FUELS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; MATERIALS; NUCLEAR FACILITIES; NUCLEAR FUELS; POWER REACTORS; REACTOR MATERIALS; REACTORS; SOLID FUELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 21 refs, 3 figs, 5 tabs
- Secondary number(s)
- IAEA-SM--358/13