To assess the feasibility of the 31% Pu-MOX fuel rod design of reduced-moderation water reactor (RMWR) in terms of thermal and mechanical behaviors, a single rod assumed to be irradiated in the core of RMWR up to 106 GWd/tHM has been analyzed by a fuel performance code FEMAXI-RM which is an extended
โฆ LIBER โฆ
Performance-related characteristics of water reactor fuel
โ Scribed by H. Bairiot; Y. Vanderborck; G. Dumbruch
- Publisher
- Elsevier Science
- Year
- 1982
- Tongue
- English
- Weight
- 708 KB
- Volume
- 106
- Category
- Article
- ISSN
- 0022-3115
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