Published September 1983
| Version v1
Report
Open
Examination of irradiated high-U-loaded U3O8-Al fuel plates
Creators
- 1. Oak Ridge National Laboratory, Oak Ridge, TN (United States)
- 2. Argonne National Laboratory, Argonne, IL (United States)
Description
Lowering the U235 enrichment level of fuels for research and test reactors requires increasing the total uranium loading. This paper presents results to date on the examination of U3O8-Al fuels with up to 75 wt % U3O8 and fission densities at about 2.3 x 1027 fissions/m3. Satisfactory performance was obtained to fission densities of about 2 x 1027 fissions/m3 at which level blistering occurred. This fission density obtained with U235 enrichment of 45% is well beyond the calculable limit for 75 wt % U3O8 with 20% U235 of 1.3 x 1027 fissions/m3. (author)
Files
36043315.pdf
Files
(868.9 kB)
| Name | Size | Download all |
|---|---|---|
|
md5:84e1f4f506917a2516dfcac09522c059
|
868.9 kB | Preview Download |
Additional details
Publishing Information
- Imprint Title
- Proceedings of the international meeting on research and test reactor core conversions from HEU to LEU fuels
- Imprint Pagination
- 723 p.
- Journal Page Range
- p. 79-87
- Report number
- ANL/RERTR/TM--4
Conference
- Title
- International meeting on research and test reactor core conversions from HEU to LEU fuels
- Dates
- 8-10 Nov 1982
- Place
- Argonne, IL (United States)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 36043315
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALUMINIUM ALLOYS; BURNUP; FISSION YIELD; FUEL PLATES; HIGHLY ENRICHED URANIUM; MODERATELY ENRICHED URANIUM; URANIUM OXIDES U3O8
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; ALLOYS; CHALCOGENIDES; ELEMENTS; ENRICHED URANIUM; FUEL ELEMENTS; ISOTOPE ENRICHED MATERIALS; MATERIALS; METALS; NUCLEAR REACTION YIELD; OXIDES; OXYGEN COMPOUNDS; REACTOR COMPONENTS; URANIUM; URANIUM COMPOUNDS; URANIUM OXIDES; YIELDS
Optional Information
- Contract/Grant/Project number
- Contract W-31-109-Eng-38
- Notes
- 5 refs, 4 figs, 1 tab
- Secondary number(s)
- CONF--821155; INIS-XA-C--020