Development of a freeze-drying process of waste-solution, 2
Creators
- 1. Power Reactor and Nuclear Fuel Development Corp., Tokai, Ibaraki (Japan). Tokai Works
Description
The waste solution treatment process in Plutonium Conversion Development Facility (PCDF) consists of Evaporation-Condensation and Neutrazation-Agglometation-Precipitation process, which produces the distillate as recovered acid at first step and separates Pu-U element from condenced solution at second step. This process needs many stages to get high decontamination efficiency and then the Evaporator is in very corrosive state because the nitric acid solution is heated over 100 degrees C to be evaporated. So, in PCDF, it was started the development of Freeze-Drying process to waste solution treatment. This process is suitable for a little quantity of the solution including nitric acid as produced in the Microwave Heating method. Moreover the process has high decontamination efficiency and has good performance of equipment. The result of the cold test of Freeze-Drying process with nitric acid is discribed in this paper. (author)
Additional details
Publishing Information
- Journal Title
- Donen Giho
- Journal Issue
- no.65
- Series
- Donen Giho.
- ISSN
- 0289-6605
- CODEN
- DOGIE
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 19073398
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- DECONTAMINATION; EFFICIENCY; FREEZING; FUEL CYCLE CENTERS; LIQUID WASTES; LYOPHILIZATION; NITRIC ACID; PLUTONIUM COMPOUNDS; PNC; RADIOACTIVE WASTES
- Descriptors DEC
- ACTINIDE COMPOUNDS; CLEANING; HYDROGEN COMPOUNDS; INORGANIC ACIDS; INORGANIC COMPOUNDS; JAPANESE ORGANIZATIONS; MATERIALS; NATIONAL ORGANIZATIONS; NITROGEN COMPOUNDS; NUCLEAR FACILITIES; OXYGEN COMPOUNDS; RADIOACTIVE MATERIALS; TRANSURANIUM COMPOUNDS; WASTES