Thermal stress analysis of an Am/Cm stabilization bushing melter
Description
Decades of nuclear material production at the Savannah River Site (SRS) has resulted in the generation of large quantities of the isotopes Am243 and Cm244. Currently, the Am and Cm isotopes are stored as a nitric acid solution in a tank. The Am and Cm isotopes have great commercial value but must be transferred to the Oak Ridge National Laboratory (ORNL) for processing. The nitric acid solution contains other isotopes and is intensely radioactive, which makes storage a problem and precludes shipment in the liquid form. In order to stabilize the material for onsite storage and to permit transport the material from SRS to ORNL, it has been proposed that the Am and Cm be separated from other isotopes in the solution and vitrified. The vitrification process in the Platinum-Rhodium alloy vessel generates a wide spectrum of temperature distributions. The melter is partially supported by a suspension system and confined by the flexible insulation. The combination of the fluctuation of temperature distribution and variable boundary conditions, induces stresses and strains in the melter. The thermal stress analysis is carried out with the finite element code ABAQUS. This analysis is closely associated with the design, manufacture and testing of the melter. The results were compared with the test data
Availability note (English)
Available from INIS in electronic form and/or on microfiche ; Also available from OSTI as DE97060145; NTIS; US Govt. Printing Office Dep.Files
29006850.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 24 p.
- Report number
- WSRC-MS--96-0591
Conference
- Title
- American Society of Mechanical Engineers (ASME) pressure vessel and piping conference.
- Dates
- 27 Jul - 1 Aug 1997.
- Place
- Orlando, FL (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 29006850
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AMERICIUM 243; CERAMIC MELTERS; COMPUTERIZED SIMULATION; CURIUM 244; RADIOACTIVE WASTE PROCESSING; SAVANNAH RIVER PLANT; STRESS ANALYSIS; TEMPERATURE DISTRIBUTION; THERMAL STRESSES; VITRIFICATION
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; AMERICIUM ISOTOPES; CURIUM ISOTOPES; ELECTRIC FURNACES; EVEN-EVEN NUCLEI; FURNACES; HEAVY NUCLEI; ISOTOPES; MANAGEMENT; NATIONAL ORGANIZATIONS; NUCLEI; ODD-EVEN NUCLEI; RADIOISOTOPES; SIMULATION; SPONTANEOUS FISSION RADIOISOTOPES; STRESSES; US AEC; US DOE; US ERDA; US ORGANIZATIONS; WASTE MANAGEMENT; WASTE PROCESSING; YEARS LIVING RADIOISOTOPES
Optional Information
- Contract/Grant/Project number
- Contract AC09-89SR18035
- Funding organization
- USDOE, Washington, DC (United States).
- Secondary number(s)
- CONF-970726--15.