Research program on development of advanced treatment technology for americium-containing aqueous waste in NUCEF
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Description
A research program was prepared on the development of an advanced treatment process for the americium-containing concentrated aqueous waste in NUCEF, than allows americium recovery for the reuse and the reduction of TRU waste generation. A preliminary analysis was conducted on the separation requirements based on the components estimated for the waste. An R and D strategy was proposed from the view to reduce TRU waste generated in the processing that the highest priority is given on the control of TRU leakage such as americium into the effluent stream after americium recovery and the minimization of salt used in the separation over the decontamination of impurities from americium. The extraction chromatographic method was selected as a candidate technology for americium separation under the principle to use reagents that are functional in acidic conditions such as bidentate extractants of DHEDECMP, CMPO or diamides, considering the larger flexibilities in process modification and possible multi-component separation with compact equipment and the past achievements on the recovery of kg quantities of americium. Major R and D items extracted are screening and evaluation of extractants for americium and plutonium, optimization of separation conditions, selection of denitration method, equipment developments and development of solidification methods of discarded americium after reuse and of various kinds of separation residues. In order to cope these items, four steps of R and D program were proposed, i.e., fundamental experiment in beaker-scale on screening and evaluation of extractants, flowsheet study in bench-scale using simulated and small amount of americium aqueous waste solution to evaluate candidate process, americium recovery test in iron-shielded cell to be installed in NUCEF. It is objected to make recovery of 100g orders of americium used for research on fundamental TRU fuel properties. (J.P.N.)
Availability note (English)
MF available from INIS under the Report Number.Files
28027517.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 50 p.
- Report number
- JAERI-Tech--96-047
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 28027517
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- ALPHA-BEARING WASTES; AMERICIUM; CHELATES; COPRECIPITATION; DISTRIBUTION FUNCTIONS; EXTRACTION CHROMATOGRAPHY; FUEL CYCLE; HIGH-LEVEL RADIOACTIVE WASTES; ION EXCHANGE; LIQUID WASTES; RADIOACTIVE WASTE PROCESSING; SOLVENT EXTRACTION
- Descriptors DEC
- ACTINIDES; CHROMATOGRAPHY; COMPLEXES; ELEMENTS; EXTRACTION; MANAGEMENT; MATERIALS; METALS; PRECIPITATION; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; SEPARATION PROCESSES; TRANSPLUTONIUM ELEMENTS; TRANSURANIUM ELEMENTS; WASTE MANAGEMENT; WASTE PROCESSING; WASTES