Beyond 5% enrichment limit for PWR 17x17 and VVER-440 fuel - Criticality problems - 14207
- Vuje, Inc., Okruzna 5, 918 64 Trnava (Slovakia)
The fuel suppliers improve permanently fuel for commercial energetic nuclear reactors. One way is to increase initial enrichment of U{sup 235}. Higher initial enrichment of U{sup 235} allows to increase burnup of assembly, to prolong stay in assembly in reactor and therefore decrease number of fresh assemblies loaded into reactor and decrease number of spent fuel assemblies for storage and disposal. In this article are some criticality analyses for fresh fuel PWR 17x17 and VVER-440 for enrichment up to 6% of U{sup 235} without burnable absorber: - Criticality of fresh assembly (PWR 17x17 and VVER-440) in cold state in reactor - Critical number of fresh assemblies (PWR 17x17 and VVER-440) in water - Possible storage and transport of fresh fuel VVER-440 in existing facilities and transport cask The SCALE 6.1.2 system was used for all calculation. The KENO VI module was used with library v7-238 (continuous energy). (author)
- Research Organization:
- American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 23100806
- Resource Relation:
- Conference: ICNC 2015: 2015 International Conference on Nuclear Criticality Safety, Charlotte, NC (United States), 13-17 Sep 2015; Other Information: Country of input: France; 3 refs.; available on CD Rom from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)
- Country of Publication:
- United States
- Language:
- English
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