Dissolution of uranium with the fuel treatment system of NUCEF
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Description
We prepared 150kgU of 10%235U uranium solution for the critical assemblies (STACY, TRACY) by dissolution of mixture 1.5%235U uranium dioxide pellets and 12%235U uranium dioxide pellets with the fuel treatment system of NUCEF. In order to find optimum operation conditions for dissolution, we carried out preliminary experiment using each one pellet and characteristic experiment using dissolver. In this report, results of these experiments and operation were described. As a result of these experiments, we obtained following operation conditions; initial nitric acid 7M, temperature 80degC, operation time 8h. Under these conditions, we dissolved UO2 of over 99% satisfactorily and prepared 150kgU of fuel solution. (author)
Availability note (English)
MF available from INIS under the Report Number.
Files
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Additional details
Publishing Information
- Imprint Pagination
- 52 p.
- Report number
- JAERI-Tech--95-038
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 27000306
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- BENCH-SCALE EXPERIMENTS; CHEMICAL PREPARATION; DISSOLUTION; DISSOLVERS; FUEL PELLETS; MODERATELY ENRICHED URANIUM; NITRIC ACID; OPTIMIZATION; SLIGHTLY ENRICHED URANIUM; SOLUTIONS; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; CHALCOGENIDES; DISPERSIONS; ELEMENTS; ENRICHED URANIUM; EQUIPMENT; HOMOGENEOUS MIXTURES; HYDROGEN COMPOUNDS; INORGANIC ACIDS; INORGANIC COMPOUNDS; ISOTOPE ENRICHED MATERIALS; MATERIALS; METALS; MIXTURES; NITROGEN COMPOUNDS; OXIDES; OXYGEN COMPOUNDS; SYNTHESIS; URANIUM; URANIUM COMPOUNDS; URANIUM OXIDES