![]() ![]() The numbers are for extraction by 20% TBP in kerosene. Partition coefficients (ratios of concentrations in the organic and aqueous phase, respectively) of Th, U, and Pu, as well as for some more problematic fission products. It is to be noted that the zircaloy cladding was found to be sufficiently resistant to corrosion by the ‘thorium reagent.’ 116įigure 8. In addition, a reduction in the dissolution time by a factor 2 may be obtained by adding about 1.5% MgO to the fuel (which also enhances sintering of the pellets 3 Section 3.04.4.1). Aluminum ions are added (as Al(NO 3) 3) to reduce this problem by forming a complex with the fluoride.ĭissolution of the fuel may be further enhanced by starting from a lower sintered density compared with that of UO 2-based fuel. However, the fluoride also facilitates corrosion of the stainless steel reactor vessels. 5,119 Here, the fluoride (as HF) is added to the nitric acid solution in order to catalyze dissolution. Spent thorium fuel is instead dissolved using the ‘THOREX reagent’ (13 M HNO 3 + 0.03–0.05 M F − + 0.1 M Al 3+). The high stability of the ThO 2 matrix, which is an advantage when considering in-pile behavior and waste disposal, renders ThO 2 and (Th,U)O 2 practically insoluble in nitric acid. The THOREX process was developed to separate fissile uranium from the fertile thorium matrix, in analogy with the PUREX process. Klaassen, in Comprehensive Nuclear Materials, 2012 3.04.6.1 The THOREX Process ![]()
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