Salt distiller with mesh-covered crucible for electrorefiner uranium deposits
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
Distillation process was employed for the cathode processing. It is very important to increase the throughput of the salt separation system due to the high uranium content of spent nuclear fuel and high salt fraction of uranium dendrites. In this study, a mesh-covered crucible was investigated for the sat distillation of electrorefiner uranium deposits. A liquid salt separation step and a vacuum distillation step were combined for salt separation. The operation time could be reduced by the use of the mesh-covered crucible and the combined operation of the two steps. A method to preserve a vacuum level was proposed by double O-rings during the operation of the distiller with the mesh-covered crucible. After the salt distillation, the salt content was measured and was below 0.1wt% after the salt distillation.
Additional details
Publishing Information
- Publisher
- KRS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the Conference and Symposium Korean Radioactive Waste Society Spring Meeting 2017
- Imprint Pagination
- 420 p.
- Journal Page Range
- p. 83
Conference
- Title
- 2017 Spring Meeting of Korean Radioactive Waste Society
- Dates
- 24-26 May 2017
- Place
- Daejeon (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 49091820
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CATHODES; COOLING; DENDRITES; ELECTROREFINING; MELTING; REPROCESSING; URANIUM DEPOSITS
- Descriptors DEC
- CRYSTALS; ELECTRODES; ELECTROLYSIS; GEOLOGIC DEPOSITS; LYSIS; MINERAL RESOURCES; PHASE TRANSFORMATIONS; PROCESSING; REFINING; RESOURCES; SEPARATION PROCESSES
Optional Information
- Notes
- 4 refs, 2 figs, 1 tab