N-Reactor (U-metal) Fuel Characteristics for Disposal Criticality Analysis
DOE-owned spent nuclear fuels encompass many fuel types. In an effort to facilitate criticality analysis for these various fuel types, they were categorized into nine characteristic fuel groups with emphasis on fuel matrix composition. Out of each fuel group, a representative fuel type was chosen for analysis as a bounding case within that fuel group. Generally, burnup data, fissile enrichments, and total fuel and fissile mass govern the selection of the representative or candidate fuel within that group. Additionally, the criticality analysis will also require data to support design of the canister internals, thermal, and radiation shielding. The purpose of this report is to consolidate and provide in a concise format, material and information/data needed to perform supporting analyses to qualify N-Reactor fuels for acceptance into the designated repository. The N Reactor fuels incorporate zirconium cladding and uranium metal with unique fabrication details in terms of physical size, and method of construction. The fuel construction and post-irradiation handling have created attendant issues relative to cladding failure in the underwater storage environment. These fuels were comprised of low-enriched metal (0.947 to 1.25 wt% 235U) that were originally intended to generate weapons-grade plutonium for national defense. Modifications in subsequent fuel design and changes in the mode of reactor operation in later years were focused more toward power production.
- Research Organization:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- DE-AC07-99ID-13727
- OSTI ID:
- 911535
- Report Number(s):
- DOE/SNF/REP-056; INEEL/MIS-00-00373; TRN: US0704616
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
CONSTRUCTION
CONTAINERS
CRITICALITY
FABRICATION
MODIFICATIONS
NATIONAL DEFENSE
N-REACTOR
NUCLEAR FUELS
PLUTONIUM
POWER GENERATION
RADIATIONS
REACTOR OPERATION
SHIELDING
STORAGE
URANIUM
ZIRCONIUM
SPENT FUELS
fuel matrix composition
spent nuclear fuels