Published April 1992
| Version v1
Report
PIE data for HEU (93%) aluminide and oxide fuels
Description
Post-irradiation-examination data are summarized for HEU (93%) UAlx-Al dispersion fuel with up to 1.7 g U/cm3 and for HEU (93%) U3O8-Al dispersion fuel with up to 1.2 g U/cm3. (author). 14 refs, 6 figs, 2 tabs
Additional details
Publishing Information
- Imprint Title
- Research reactor core conversion guidebook. V. 4: Fuels (Appendices I-K)
- Imprint Pagination
- 594 p.
- Journal Page Range
- p. 197-204.
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--643(v.4)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 23087396
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ALUMINIUM; DENSITY; DISPERSION NUCLEAR FUELS; POST-IRRADIATION EXAMINATION; RESEARCH REACTORS; URANIUM; URANIUM OXIDES U3O8
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; CHALCOGENIDES; ELEMENTS; ENERGY SOURCES; FUELS; MATERIALS; METALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SOLID FUELS; URANIUM COMPOUNDS; URANIUM OXIDES