Burnup credit applications in a high-capacity truck cask
Description
The use of burnup credit in the criticality safety analysis of the GA-4 Cask increases the cask's capacity from three spent fuel assemblies to four, resulting in reduced public and occupational risk and reduced life cycle costs. GA's criticality calculations for burnup credit, including the associated uncertainties and analytical bias, establish the minimum burnup required as a function of initial enrichment to maintain Keff ≤ 0.95 under any conceivable condition. The minimum burnup requirement as a function of initial enrichment has been determined to be 15,000 MWd/MTU for 3.5 wt% U-235 fuel, 20,000 MWd/MTU for 4.0 wt% U-235 fuel and 25,000 MWd/MTU for 4.5 wt% U-235 fuel. The minimum burnup requirement as a function of enrichment is well below the typical burnup levels seen in the current and projected spent fuel inventory. (J.P.N.)
Files
Additional details
Publishing Information
- Imprint Title
- The 10th international symposium on the packaging and transportation of radioactive materials
- Imprint Pagination
- 1709 p.
- Journal Page Range
- v. 3 p. 1545-1551.
- Report number
- INIS-JP--018
Conference
- Title
- 10. international symposium on the packaging and transportation of radioactive materials.
- Acronym
- PATRAM'92
- Dates
- 13-18 Sep 1992.
- Place
- Yokohama (Japan).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 25055653
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; BWR TYPE REACTORS; CAPACITY; CASKS; CRITICALITY; DESIGN; PWR TYPE REACTORS; ROAD TRANSPORT; SAFETY ANALYSIS; SPENT FUELS
- Descriptors DEC
- CONTAINERS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; LAND TRANSPORT; MATERIALS; NUCLEAR FUELS; POWER REACTORS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; TRANSPORT; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Composed of three volumes.