Status on the development of Mo 99 production technology using low enriched uranium
Description
The technology for Mo 99 production using uranium target consists of three main steps of target fabrication, target irradiation in a research reactor, and chemical process for Mo 99 separation. Basically the HEU based technology might be utilized for LEU based target without a significant change. But there are some of disadvantages to be overcome on the use of LEU target such as more radioactive wastes and a lower purity of Mo 99 product. In addition, there are no much experiences on LEU based technology for commercial mass production with a good quality. As a result of research by Argonne National Lab., USA, a new LEU target was proposed to be able to substitute a HEU target. It uses a uranium metal foil in between aluminum clad as a target material and is shaped in annular type for a good structural integrity and an easier disassembly after irradiation. In addition, KAERI invented a novel technology by which a continuous production of the uranium foil is possible and an economical efficiency on target fabrication is solved. The IAEA launched a Cooperative Research Program (CRP) on the technique development for small scale, indigenous production of Mo 99 in 2005 in order to demonstrate the Mo 99 production technology using LEU metal foil as a target material. Based on the research and development that have been done until now, there are no significant issues on fabrication and irradiation in a reactor of LEU metal foil target. The Mo 99 separation test will be performed soon. For the purity of Mo 99 product, it is reported that the amount of alpha emitters in the irradiated LEU target is only slightly higher than that in the HEU target if all Pu and U are included. The only remaining major issue that has to be developed for the LEU base Mo 99 production is the Mo 99 separation technology using modified Cintichem process and its optimization for large scale production. This requires many separation experiments from cold to hot tests and improvements from the experiences
Additional details
Publishing Information
- Publisher
- KAIF-KNS
- Imprint Place
- Seoul (Korea, Republic of)
- Imprint Title
- Proceedings of the 24th KAIF/KNS Annual Conference
- Imprint Pagination
- 667 p.
- Journal Page Range
- p. 409-414
Conference
- Title
- 24. KAIF/KNS Annual Conference
- Dates
- 8-10 Apr 2009
- Place
- Seoul (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 44066874
- Subject category
- S07: ISOTOPES AND RADIATION SOURCES; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ENRICHED URANIUM; FABRICATION; IRRADIATION; MOLYBDENUM 99; PRODUCTION; RADIOACTIVE WASTES
- Descriptors DEC
- ACTINIDES; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; DAYS LIVING RADIOISOTOPES; ELEMENTS; EVEN-ODD NUCLEI; INTERMEDIATE MASS NUCLEI; ISOTOPE ENRICHED MATERIALS; ISOTOPES; MATERIALS; METALS; MOLYBDENUM ISOTOPES; NUCLEI; RADIOACTIVE MATERIALS; RADIOISOTOPES; URANIUM; WASTES
Optional Information
- Notes
- 9 refs, 2 figs