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AbstractAbstract
[en] Existing Dry Spent Fuel Casks (DSC) for transporting and storing of Armenian NPP fuel was licensed for WWER-440 fuel assemblies with 3.6% enrichment. Having in mind that ANPP introduced new fuel assemblies with increased enrichment (3.82 %) re-assessment of criticality safety analysis for DSC is required. Criticality safety analysis of DSC was performed by KENO-VI program using 238-GROUP ENDF/B-VII.0 LIBRARY (V7-238). Results of analysis showed that additional 8 borated racks for fuel assemblies should be included in the design of DSC. In addition feasibility study was performed to find out level of burnup-credit approach implementation to keep current design of DSC unchanged. Burnup-credit analysis was performed by STARBUCS program using axial burnup profiles from Armenian NPP neutronics analysis carried out by BIPR code. (authors)
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Source
2013; 11 p; 10. International conference on WWER fuel performance, modelling and experimental support; Sandanski (Bulgaria); 7-14 Sep 2013; 1 fig., 13 refs., 2 tabs.
Record Type
Miscellaneous
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Conference
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ACTINIDES, CASKS, CONTAINERS, ELEMENTS, ENERGY SOURCES, ENRICHED URANIUM, ENRICHED URANIUM REACTORS, FUELS, ISOTOPE ENRICHED MATERIALS, MATERIALS, METALS, NUCLEAR FACILITIES, POWER PLANTS, POWER REACTORS, PWR TYPE REACTORS, REACTOR MATERIALS, REACTORS, THERMAL POWER PLANTS, THERMAL REACTORS, URANIUM, WATER COOLED REACTORS, WATER MODERATED REACTORS
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