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Some aspects of 233U enriched fuel for light water reactors

✍ Scribed by Yigal Ronen; Moshe Cojocaru


Publisher
Elsevier Science
Year
1978
Tongue
English
Weight
96 KB
Volume
5
Category
Article
ISSN
0306-4549

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The performance of natural uranium and thorium-fueled fast breeder reactors (FBRs) for producing 233 U fissile material, which does not exist in nature, is investigated. It is recognized that excess neutrons from FBRs with good neutron economic characteristics can be efficiently used for producing 2