METHOD OF PRODUCTION OF THE CARRIER-FREE STROTIUM-90 WITH USAGE OF THE NUCLEAR WATER-SOLUTION REACTOR AND THE DEVICE FOR THE METHOD REALIZATION Russian patent published in 2007 - IPC C01F11/00 G21G1/00 

FIELD: chemical industry; methods and the devices for production of the carrier-free strontium-90.

SUBSTANCE: the invention is pertaining to production of the radionuclides and may be used for production of the carrier-free strontium-90. The device for production of the carrier-free strontium-90 with usage of the nuclear water-solution reactor includes: the nuclear water-solution reactor (23) with the located above its active zone (1)compensation chamber (9), the inlet pipeline (15), the compressor (10), the apparatus (2) for the gaseous medium curing, the outlet pipeline (14) and all mounted in the line of circulation of the gaseous medium. The compensation chamber (9) intended for compensation of the temperature dilations of the fuel solution during operation of the nuclear water-solution reactor (23) is filled with the gaseous medium, the composition of which includes the gaseous products of the fission of the nuclear fuel and the volatile compounds of the radionuclides. In the apparatus (2) for the gaseous medium curing the gaseous medium is pumped over together with the present in it dissolvent of strontium. During pumping of the gaseous medium through the apparatus (2) for the gaseous medium curing store the carrier-free strontium-90 in the dissolvent of the strontium. The composition of the apparatus (2) used foe the gaseous medium curing includes: the hydraulic pump (5) for pumping the dissolvent of strontium over, the pressure vessel (12), the pipeline (22) for the joint pumping of the gaseous medium and the dissolvent of strontium, and the expansion vessel (17) with the gaseous chamber (8) located in its upper part. At that the compensation chamber (9) of the nuclear water-solution reactor (23) is connected to the pressure pot (12) by the inlet pipeline (15), the pressure pot (12) is connected to the gaseous chamber (8) of the expansion vessels (17) by the pipeline (22) for the joint pumping of the gaseous medium and the dissolvent of strontium, the compensation chamber (8) of the expansion vessels (17) is connected to the compensation chamber (9) of the nuclear water-solution reactor (23) by the outlet pipeline (14). The technical result of the invention is production of the fully processed product in the form of the solution of the carrier-free strontium-90, the absence of the screen for trapping of the gaseous particles of rubidium and strontium.

EFFECT: the invention ensures production of the fully processed product made in the form of the solution of the carrier-free strontium-90, the absence of the screen for trapping of the gaseous particles of rubidium and strontium.

8 cl, 1 dwg, 1 ex