Safety research of multi-functional reprocessing process considering nonproliferation based on an ion-exchange method
- Japan Atomic Energy Agency - JAEA, 4002, Narita O-arai Ibaraki 311-1393 (Japan)
- Japan Atomic Energy Agency - JAEA (Japan)
- National Institute of Advanced Industrial Science and Technology - AIST (Japan)
- KAKEN Co., Ltd (Japan)
- Japan Atomic Energy Agency - JAEA, National Institute of Advanced Industrial Science and Technology - AIST, Tokyo Institute of Technology - Tokyo Tech (Japan)
A simplified separation process was proposed based on an ion-exchange technique. A tertiary pyridine-type ion-exchange resin was used in this process to treat the mixed oxide fuel highly irradiated in the experimental fast reactor 'JOYO'. It was demonstrated that the process is a realistic candidate for future reprocessing using hydrochloric acid and a mixed eluent solution of nitric acid and methanol. In order to develop an engineering scale concept, it is indispensable to establish the conditions for safe operation, so two types of experiments were done to obtain fundamental aspects. The corrosion experiment for structural materials in hydrochloric acid at room temperature was done using tantalum, zirconium, niobium, hastelloy and SUS316L. Results showed that tantalum, zirconium, niobium, and hastelloy had good corrosion resistance to hydrochloric acid. The second experiment looked at the thermal hazards of pyridine-type ion-exchange resin and the methanol, or nitric acid eluent system from the viewpoints of fire and explosion safety. No hazardous reactions occurred between the resin and the eluent system. Above 150 deg. C, attention should be paid to the exothermic reactions for the dried resin. (authors)
- Research Organization:
- American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 20979732
- Resource Relation:
- Conference: Advanced nuclear fuel cycles and systems (GLOBAL 2007), Boise - Idaho (United States), 9-13 Sep 2007; Other Information: Country of input: France; 6 refs; Related Information: In: Proceedings of GLOBAL 2007 conference on advanced nuclear fuel cycles and systems, 1873 pages.
- Country of Publication:
- United States
- Language:
- English
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