Comparison of subcriticality of the interim spent fuel storage before and after modification
Description
Full text: After political and economical changes in the end of eighties, the utility operating the nuclear power plants in Slovakia decided to change original scheme of the back-end of the nuclear cycle; instead of reprocessing in the USSR/Russia spent fuel will be stored in an interim spent fuel storage facility until the time of the final decision. As the best solution, a modification of the existing interim storage has been realised. In existing interim storage is used new basket with new shape and with compact racks from boron steel. In Slovakia they are in operations 6 units WWER-440. The original capacity of the interim storage is 5040 assemblies, after modification is 14,112 assemblies. The original type of fuel (used in operation and stored in the interim storage) has maximal enrichment 3.6%. The current type of fuel (now used only in operation, not in storage) has radial profiled enrichment with maximum 4.0%. The advanced fuel (will be in operation after 2005) has maximal enrichment 4.4%. The subcriticality both baskets with different fuel by operational conditions: C-30 KZ-48 3.6% 0.85287 0.83384 4.4% 0.88489 0.87477. In article are compared criticality both baskets by abnormal conditions: mechanical destruction or loss of coolant. New basket make possible to increase 2,8 times the capacity of interim storage and is more safety than older one. (author)
Additional details
Publishing Information
- Imprint Title
- International conference on storage of spent fuel from power reactors. Book of extended synopses
- Imprint Pagination
- 140 p.
- Journal Page Range
- p. 77
- Report number
- IAEA-CN--102
Conference
- Title
- International conference on storage of spent fuel from power reactors
- Dates
- 2-6 Jun 2003
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 34047366
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRITICALITY; FUEL CYCLE; SLIGHTLY ENRICHED URANIUM; SLOVAK ORGANIZATIONS; SPENT FUEL CASKS; SPENT FUEL STORAGE; WWER TYPE REACTORS
- Descriptors DEC
- ACTINIDES; CASKS; CONTAINERS; ELEMENTS; ENRICHED URANIUM; ENRICHED URANIUM REACTORS; ISOTOPE ENRICHED MATERIALS; MATERIALS; METALS; NATIONAL ORGANIZATIONS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; STORAGE; THERMAL REACTORS; URANIUM; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 3 refs
- Secondary number(s)
- IAEA-CN--102/42P