Irradiation experiments
Description
Irradiation experiments conducted in 1972-1973 in the OSIRIS reactor on fuel plates containing 93% enriched uranium are described. Eight plates contained UAl3-Al fuel with 35 wt% U (1.3 g U/cm3) and 43 wt% U (1.7 g U/cm3) and two plates contained U3O8-Al fuel with 43 wt% U (1.7 g U/cm3). The average burnup of the 235U was 58.5% and the maximum burnup was 70%. Results of the post-irradiation-examinations include data on dimensional measurements and metallographic examinations, the influence of grain size and the percentage of fines below 40 microns in the UAl3-Al plates with 35 wt% U, and the minimum temperature at which swelling appears with the occurrence of blisters after post-irradiation annealing. All of the tested plates behaved satisfactorily under irradiation. (author). 2 refs, 3 figs, 4 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. 217-228.
- 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
- 23087398
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ALUMINIUM; BLISTERS; BURNUP; DISPERSION NUCLEAR FUELS; FUEL PLATES; HIGHLY ENRICHED URANIUM; OSIRIS REACTOR; POST-IRRADIATION EXAMINATION; SWELLING; TEMPERATURE DEPENDENCE
- Descriptors DEC
- ACTINIDES; DEFORMATION; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; FUELS; IRRADIATION REACTORS; ISOTOPE ENRICHED MATERIALS; MATERIALS; MATERIALS TESTING REACTORS; METALS; NUCLEAR FUELS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SOLID FUELS; TANK TYPE REACTORS; THERMAL REACTORS; URANIUM; WATER COOLED REACTORS; WATER MODERATED REACTORS