Treatment of molten chloride waste salt from pyrometallurgical process
- 1. Komae Research Lab., Tokyo (Japan)
Description
Chloride waste salt arises from pyrometallurgical processes for high level radioactive liquid waste (HAW) treatment. The immobilization of the waste has been developed experimentally using simulated salts by the following three stages: (1) Li recovery from the salts into a liquid Cd cathode by electrolysis, followed by (2) fission products (FPs) and Na recovery into a liquid Pb cathode by electro-reduction. Finally, (3) the recovery of the metal elements by air oxidation to separate into oxide slag. This slag can be stabilized as borosilicate glass. Lithium was recovered into the Cd cathode efficiently from the simulated waste salt by electro-reduction in the Li recovery stage. In the FPs and Na recovery stage almost all the residual metal elements were further recovered from the waste salt, composed of mainly CsCl, using the liquid Pb cathode by electrolysis. In the final Pb alloy oxidation stage, all the metal elements in the Pb alloy was also removed into the oxide slag
Additional details
Publishing Information
- Imprint Title
- Technology and programs for Radioactive Waste Management and Environmental Restoration. Volume 1
- Imprint Pagination
- 814 p.
- Journal Page Range
- p. 775-779.
- Report number
- CONF-940225--Vol.1
Conference
- Title
- working towards a cleaner environment.
- Acronym
- Waste management '94
- Dates
- 27 Feb - 3 Mar 1994.
- Place
- Tucson, AZ (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27016222
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BOROSILICATE GLASS; CADMIUM; CATHODES; CESIUM 137; ELECTROLYSIS; FISSION PRODUCTS; HIGH-LEVEL RADIOACTIVE WASTES; LEAD ALLOYS; LITHIUM; OXIDATION; RADIOACTIVE WASTE PROCESSING; SALTS; SEPARATION PROCESSES; SILICON OXIDES; STRONTIUM 90; WASTE FORMS
- Descriptors DEC
- ALKALI METALS; ALLOYS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CESIUM ISOTOPES; CHALCOGENIDES; CHEMICAL REACTIONS; ELECTRODES; ELEMENTS; EVEN-EVEN NUCLEI; GLASS; INTERMEDIATE MASS NUCLEI; ISOTOPES; MANAGEMENT; MATERIALS; METALS; NUCLEI; ODD-EVEN NUCLEI; OXIDES; OXYGEN COMPOUNDS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; RADIOISOTOPES; SILICON COMPOUNDS; STRONTIUM ISOTOPES; WASTE MANAGEMENT; WASTE PROCESSING; WASTES; YEARS LIVING RADIOISOTOPES