A method of solidifying radioactive waste resin using naalo2 coagulant cement
Patent Information
- Authority / Receiving Office
- CN · China
- Current Assignee / Owner
- TSINGHUA UNIV
- Publication Date
- 2011-12-14
- Estimated Expiration
- Not applicable · inactive patent
Abstract
Description
technical field
[0001] The invention belongs to the technical field of radioactive waste resin cement solidification, in particular to a method using NaAlO 2 A method for solidifying radioactive waste resin with coagulant cement. Background technique
[0002] In nuclear power plants, ion exchange technology is widely used in auxiliary systems of the primary and secondary circuits and radioactive waste liquid treatment systems. Due to the high radioactive level of the loaded nuclides or the saturation of the exchange capacity, the resin in the equipment needs to be replaced regularly. Waste resin must be cured before final disposal. Cement solidification technology is the main solidification method of radioactive waste resin, but the waste containment capacity is low. Especially when solidifying the boron-containing waste resin produced by the pressurized water reactor nuclear power plant, the increase in the containment capacity will increase the amount of boron contained ...