HEU to LEU fuel conversion. Final report
Description
The Nuclear Regulatory Commission issued a ruling, effective March 27, 1986, that all U.S. non-power reactors convert from HEU fuel to LEU fuel. A Reduced Enrichment for Research and Test Reactors Program was conducted by the Department of Energy at Argonne National Laboratory to coordinate the development of the high density LEU fuel and assist in the development of Safety Analysis Reports for the smaller non-power reactors. Several meetings were held at Argonne in 1987 with the non-power reactor community to discuss the conversion and to set up a conversion schedule for university reactors. EG ampersand G at Idaho was assigned the coordination of the fuel element redesigns. The fuel elements were manufactured by the Babcock ampersand Wilcox Company in Lynchburg, Virginia. The University of Virginia was awarded a grant by the DOE Idaho Operations Office in 1988 to perform safety analysis studies for the LEU conversion for its 2 MW UVAR and 100 Watt CAVALIER reactors. The University subsequently decided to shut down the CAVALIER reactor. A preliminary SAR on the UVAR, along with Technical Specification changes, was submitted to the NRC in November, 1990. An updated SAR was approved by the NRC in January, 1991. In September, 1992, representatives from the fuel manufacturer (B ampersand W) and the fuel designer (EG ampersand G, Idaho) came to the UVAR facility to observe trial fittings of new 22 plate LEU mock fuel elements. B ampersand W fabricated two non-fuel bearing elements, a regular 22 plate element and a control rod element. The elements were checked against the drawings and test fitted in the UVAR grid plate. The dimensions were acceptable and the elements fit in the grid plate with no problems. The staff made several suggestions for minor construction changes to the end pieces on the elements, which were incorporated into the final design of the actual fuel elements. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as DE95015477; NTIS; US Govt. Printing Office Dep.Files
27002022.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 731 p.
- Report number
- DOE/ER/75388--T1
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27002022
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data, Progress Report
- Descriptors DEI
- CONVERSION; EXPERIMENTAL DATA; HIGHLY ENRICHED URANIUM; LEADING ABSTRACT; POWER COEFFICIENT; PROGRESS REPORT; REACTOR FUELING; SAFETY ANALYSIS; SLIGHTLY ENRICHED URANIUM; TEMPERATURE COEFFICIENT; TESTING; UVAR REACTOR
- Descriptors DEC
- ABSTRACTS; ACTINIDES; DATA; DOCUMENT TYPES; ELEMENTS; ENRICHED URANIUM; ENRICHED URANIUM REACTORS; INFORMATION; IRRADIATION REACTORS; ISOTOPE ENRICHED MATERIALS; ISOTOPE PRODUCTION REACTORS; MATERIALS; METALS; NUMERICAL DATA; POOL TYPE REACTORS; REACTIVITY COEFFICIENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; TRAINING REACTORS; URANIUM; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract FG02-88ER75388
- Funding organization
- USDOE, Washington, DC (United States).