Sequential process test for metal pyro-processing using U, Pu, and Am
Creators
- 1. Central research Institute of Electric Power Industry, Iwadokita 2-11-1, Komae, Tokyo 201-8511 (Japan)
- 2. Japan Atomic Energy Agency, Muramatsu 4-33, Tokai-mura, Naka-gun, Ibaraki 319-1194 (Japan)
Description
The Central Research Institute of Electric Power Industry (CRIEPI) and the Japan Atomic Energy Agency (JAEA) are continuing a collaboration study for metal pyro-processing, in which sequential process tests have been performed under practical conditions using ∼1 kg of molten salt baths. Recent results on two kinds of sequential process test are reported. The former is the electro-chemical reduction test of MOX pellet in order to form U-Pu alloy ingots. The latter is the electrolysis test using a combination of U-Pu alloy anode and solid or liquid cadmium cathode to recover U-product or U-Pu-Am alloy product, respectively. Variation in electrode potentials, current efficiency, molten salt composition, Pu- or Am-impurity in the U-product, U/Pu or Am/Pu separation factor in the U-Pu alloy product, and etc. were measured. These tests reproduced practical operating conditions at a scale of ∼1/1000 that of the actual process. (author)
Availability note (English)
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40032684.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 8 p.
- Report number
- INIS-FR--09-0064
Conference
- Title
- Nuclear fuel cycle for a sustainable future
- Acronym
- Atalante 2008
- Dates
- 19-23 May 2008
- Place
- Montpellier (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 40032684
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCH-SCALE EXPERIMENTS; ELECTROMETALLURGY; ELECTROREFINING; MIXED OXIDE FUELS; MOLTEN SALTS; PLUTONIUM; PYROCHEMICAL REPROCESSING; URANIUM
- Descriptors DEC
- ACTINIDES; ELECTROLYSIS; ELEMENTS; ENERGY SOURCES; FUELS; LYSIS; MATERIALS; METALLURGY; METALS; NUCLEAR FUELS; PROCESSING; REACTOR MATERIALS; REFINING; REPROCESSING; SALTS; SEPARATION PROCESSES; SOLID FUELS; TRANSURANIUM ELEMENTS
Optional Information
- Notes
- 5 refs.