Studies of the restructuring of fast breeder test reactor fuel by out-of-pile simulation
Journal Article
·
· Nuclear Technology
OSTI ID:449620
- Indira Gandhi Centre for Atomic Research, Kalpakkam (India). Fuel Chemistry Div.
The fast breeder test reactor (FBTR) at Kalpakkam, India, currently employs a mixed carbide of uranium and plutonium with a Pu/(Pu + U) ratio of 0.70 as fuel. The behavior of this fuel in a thermal gradient is investigated. An out-of-pile simulation facility is designed, set up, and commissioned. Experiments are conducted on FBTR fuel pellets to study the restructuring of the fuel at various levels of linear power and its cracking behavior in a thermal gradient. The results are discussed in terms of their significance for reactor operation.
- OSTI ID:
- 449620
- Journal Information:
- Nuclear Technology, Journal Name: Nuclear Technology Journal Issue: 3 Vol. 117; ISSN 0029-5450; ISSN NUTYBB
- Country of Publication:
- United States
- Language:
- English
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