During the operation of a nuclear power plant, especially during conservation or decommissioning, appreciable quantities of radionuclides accumulate in the water of the holding basin for the spent fuel. This results in a high radiation background during maintenance work and creates a potential danger that the radionuclides will escape into the external environment as a result of a break in the seal of the basin casing. In particular, at the Beloyarskaya nuclear power plant, the radioactivity of the water in both regulation holding basins reached -20 GBq/m 3. The radionuclides 137Cs and t34Cs make the main contribution to the total specific radioactivity of the water: 9% and 1%, respectively. The radioactivity of other biologically toxic nuclides, such as, 9~ and 6~ is insignificant and does not exceed 0.13% of the total activity. The most efficient method for deactivation of the holding-basin water is a sorption technology. However. because of the high specific radioactivity of water and the large volume of the basins (2200 m 3 each), the traditional organic cationites will hardly be useful for purification because of their low radiation resistance [1, 2]. This justifies the interest in the synthetic inorganic sorbents, which have a high radiation resistance and selectivity [3-8]. Specifically, the granulated synthetic mordenite extracts more than 95% of ~37Cs and 134Cs and 75% of the ll0mAg from the water in the basin, after passage through 16,000 column volumes, for storage of spent fuel [3]. According to the data of [4-6], a promising inorganic sorbent for these purposes is zirconium phosphate, which is characterized by high capacity and selectivity with respect to cesium isotopes and can remain functional for a long time in the dynamic regime [5]. Its sorption capacity does not decrease under irradiation with 3' rays with a dose of 3.107 Gy [9] and neutrons with a dose of 8-105 Gy [10]. In the present paper we describe the sorpt~on-selective properties and the results of model tests of spherogranulated thermooxide-3A zirconium phosphate for the removal of 137Cs, in the circulation regime, from the simulator of the water in the holding basin of a Beloyarskaya nuclear power plant. This phosphate (the chemical composition is Zr(HPO4)2"H20 (the ratio P/Zr = 2)) was synthesized by the sol-gel method [5]. Externally, it consists of spherical 0.4-1 mm glassy granules, with a bulk density of 1.1 g/cm 3, a moisture content of 32% if dried at ll0~ and a mechanical strength of 15 4- 3 MPa. The pH-metric tritration curves for alkali (Na + and Cs +) and alkaline-earth cations (Ca 2 +. Mg 2 +) for pH ranging from 2 to 8 were measured in order to investigate the sorption-selective properties, and the distribution coefficients (Dg) of 137Cs (no carrier) sorbed from 0 05 moles/liter of a NaNO 3 solution with different filling of the sorbent volume with Na +, Ca 2+, and Mg 2+ as well as the internal diffusion coefficient of cesium cations in the pores of the sorbent were determined. The titration curves were obtained by the method of separate measured quantities of the chloride solution with a constant ionic strength of the solutions 0.1 N. the solid:liquid ratio equal to 1 g:50 cm 3 for alkali cations and 0.2-0.4 g:50 cm 3 for alkalineearth cations, and a solution holding time of six days. Solid magnesium oxide was used to change the pH in the system H+--Mg 2 +. and solutions of the corresponding alkali were used for the other cations. The method of radioactive indicators was used to determine the equilibrium concentration of alkali metals. The alkahne-earth metals in the solutions were analyzed by the trilonometric method [11]. The distribution coefficient of 137Cs (no carrier) was found in a system with 0.05 moles/liter of NaNO 3 with continuous mixing for 24 h. The ",/activity of the liquid phase was measured on a Roboton 20040 radiometer. using a scintillation detector.
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