Speaker
Description
Radioactive ion exchange resin is one of the main low-intermediate level waste(LILW) generated by nuclear facilities, and it has always been a hot and difficult point in the safety management of radioactive waste. At present, the waste resin treatment technology of cement solidification process used in China can not meet the increasingly stringent requirements of waste minimization due to its large volume increase and insufficient long-term stability. The wet oxidation process of waste resin can treat waste resin as inorganic waste liquid, which can effectively achieve the goal of volume reduction and solidification after evaporation and concentration.
On the basis of previous research, China Institute for Radiation Protection has successfully built a thermal test device for wet oxidation of waste resin, and carried out on-site radioactivity test verification of radioactive waste resin at a nuclear power station in December 2020. The contact dose rate of the waste resin used in the test is 100.4SV/h, and the treatment capacity of the waste resin in a single test is 10kg. The test results show that: (1) the device runs well, basically meeting the actual demand of radioactive waste resin treatment; (2) the oxidative decomposition rate of waste resin is 99%; (3) in the process of waste resin wet oxidation, the concentration of main nuclides in condensate is lower than 1000 bq/L, and the carrier rate of main nuclides in waste gas is lower than the detection line. This experiment has laid a solid foundation for the industrialization of waste resin wet oxidation plant.
Key words: radioactive ion exchange resin; wet oxidation; device
| Speaker's title | Mr |
|---|---|
| Affiliation | China Institute for Radiation Protection |
