Fast Reactor Technology for Energy Security: Challenges for Materials Development
Author:
Affiliation:
1. National Engineering College
2. Indira Gandhi Centre for Atomic Research
Publisher
Japan Society of Mechanical Engineers
Link
https://www.jstage.jst.go.jp/article/jmmp/7/4/7_473/_pdf
Reference20 articles.
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3. 3. Structural Materials for Liquid Metal Cooled Fast Reactor Fuel Assemblies —Operational Behaviour, IAEA Technical Report No. NF-T-4.3, Vienna, 2012, pp. 1-87.
4. 4. C. Cawthrone and F. J. Foulton, Voids in Irradiated Stainless Steel, Nature, Vol. 216, 1957, pp. 575-576.
5. 5. F. A. Garner, M. B. Toloczko and B. H. Sencer, Comparison of Swelling and Irradiation Creep Behavior of FCC-Austenitic and BCC-Ferritic/Martensitic Alloys at High Neutron Exposure, Journal of Nuclear Materials, Vol. 276, 2000, pp. 123-142.
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