RELEASE OF FISSION PRODUCTS FROM DEFECTED ThO$sub 2$-UO$sub 2$ CERAMIC FUEL ELEMENTS IN A BOILING WATER REACTOR
Journal Article
·
· Nuclear Sci. and Eng.
OSTI ID:4236407
Two tests are described which were carried out in the EBWR to establish the rates of release of fission products from ThO/sub 2/-- UO/sub 2/ (stainless steel clad) fuel and to assess the magnitude of the resulting operational problems. The fuel used in both tests was 90 wt.% ThO/sub 2/--10% U/sup 235/ O/ sub 2/ in the form of pellets. In test number one the clad element was 3.1 in. long and was subjected to 3% burnup. In test number two the element was 48 in. long and was subjected to a 7% burnup. Activities of various nuclides in the reactor water and the evolution of fission product gases were measured for each test. (W.D.M.)
- Research Organization:
- Argonne National Lab., Lemont, Ill.
- NSA Number:
- NSA-13-017489
- OSTI ID:
- 4236407
- Journal Information:
- Nuclear Sci. and Eng., Journal Name: Nuclear Sci. and Eng. Vol. Vol: 2, No. 1, Suppl.
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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