Identification of fission products released from irradiated uranium/aluminum alloy fuel
Description
Out-of-pile studies of fission product release from melted reactor fuels have been carried out by inductively heating the fuel, entraining the released fission products in a flowing gas and separating the fission products in a thermal gradient tube and filters. Identification of the chemical form of each fission product is implied from its location in the apparatus and from chemical analysis of the apparatus surfaces after melting is accomplished. Determination of the chemical forms of fission products in this manner, however, does not identify the nature of the fission product within the fuel matrix or on the fuel surface. The possibility that fission products undergo vapor phase or surface reactions during the time between their release and deposition on the surface of the apparatus masks the true identity of the chemical forms of fission products within the fuel matrix or on the surface of the molten fuel
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01; 1 as DE84013963.
Files
Additional details
Publishing Information
- Imprint Pagination
- 16 p.
- Report number
- DP-MS--84-46
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16010848
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ALUMINIUM ALLOYS; CHEMICAL COMPOSITION; FISSION PRODUCT RELEASE; FUEL ELEMENTS; MELTDOWN; REACTOR SAFETY; URANIUM ALLOYS
- Descriptors DEC
- ACCIDENTS; ACTINIDE ALLOYS; ALLOYS; REACTOR ACCIDENTS; REACTOR COMPONENTS; SAFETY