Curing Volume Reduction And Mechanism Of Radioactive Waste Resin

Radioactive ion exchange resin was used in the nuclear power plant. Because of the enrichment of radiosondes, people attach great importance to it. With the development of nuclear power industry, the treatment of radioactive waste ion exchange resin becomes a problem to be solved. In this paper, the radioactive ion exchange resin was pretreated by Fenton reagent and then it was cured by geological cement.In this paper, Fenton’s reagent was used to degrade the blank ion exchange resin and the process of the ion exchange resin degraded by Fenton’s reagent was preliminarily understood. The infulencing factors on the degradation of residue in the process of degradation, such as the addition amount of Na OH solution and the adding time were explored. The influences of various kinds of anti foaming agents on the experiment were also explored and the anti foaming agent of 1488 had an obvious effect on the elimination of the bubble. The results showed that when the reaction produced a large amount of foam and the foam has a suspended substance,Na OH solution was added and the 15 g wet anion resin needed 0.7 g Na OH, in which way the residue could be reduced to a minimum. The structure and the component of the resin and its residue were determined by the fourier transform infrared spectrometer. In this paper, the effects of different experimental conditions on the degradation of Fenton’s reagent were studied. The change of the quality of the residue, the volume and TOC of the residual liquid with the variables were evaluated.The results showed that15 g wet mixed resin was dissolved in the optimal conditions,when the oil bath temperature is 95 ℃and 70 ml H2O2 with mass fraction of 30%was added. The reaction time was 1 h and the dose response was not affected.In this paper, the ion exchange resin was simulated and degraded. The fate of the radionuclides in the process of the degradation of the waste resin was studied.The resin was saturated with Cs NO3 solution for seven days to achieve the radioactive simulation. The contents of Cs in the residual liquid, the condensate, the distillation and the concentration were measured by inductively coupled plasma mass spectrometry. The results showed that the Cs was basically kept in the residual liquid and the concentrated liquid. The content of Cs in the distillate was too little to be neglected. Sodium tetraphenylborate and sodium nitrite cobalt had reactions with Cs in the condensate. The effect of the sodium tetraphenylborate was better.In this paper, the performances of ordinary cement and geological cement were compared. The radioactive waste was cured by geological cement. The strength ofthe solidified body was measured by automatic compressive and flexural spectrometry. The content of Cs in the leaching solution was measured by inductively coupled plasma mass spectrometry. The type and the content of the micro element was measured by energy dispersive spectrometer. The micro morphology of the solidified body was detected by the electron scanning microscope.The results showed that the waste liquid treated by the sodium tetraphenylborate was cured with the geological cement 4-9-2-B and the hydration ratio was 0.7. The compressive strength of the solidified body was 13.8 MPa and the leaching rate was1.4×10-3 cm/d, which meet the national standard.