Optimization design research for 89Sr production in China Experimental Fast Reactor.
As the first sodium cooled fast reactor in China, China Experimental Fast Reactor (CEFR) has many characteristics, such as high power rating, high neutron flux and high neutron leakage as its hard spectrum. These leakage neutrons can be used to produce 89Sr by fast neutrons (n, p) reaction. By means of some special designs, including designing optimized target assembly, choosing reasonable irradiation location and appropriate irradiation cycle length, in order to improve specific activity of 89Sr. The MNCP code was used to the calculations coupled ORIGRN2 procedure. The higher activity of 89Sr can be obtained by these optimization designs, so it is feasible to produce 89Sr in the fuel region of CEFR.
Analyses of production capacity of 89Sr and 90Sr in the 2 MW molten salt reactor.
The production capacity of 89Sr and 90Sr in the 2 MW MSR are evaluated. The gaseous 89Kr and 90Kr are extracted from the core through the helium bubbling system, and then decay to 89Sr and 90Sr, respectively. In order to improve purity of 89Sr product, two cooling devices are adopted in the 89Sr and 90Sr production system. The annual yields of 89Sr and 90Sr are about 9000 Ci and 32 Ci, respectively, and the impurity of 89Sr product is less than 2 ppm which can meet the medical requirement.
Improved chemistry for the production of yttrium-90 for medical applications
Abstract A novel extraction chromatographic method for the preparation of 90 Y of high chemical and radiochemical purity has been developed. After an initial purification of a 90 Sr stock solution and a suitable period of 90 Y ingrowth, the solution is passed through a series of strontium-selective chromatographic columns, each of which lowers the 90 Sr content of the mixture by a factor of ∼ 10 3 . The 90 Y remaining is freed from any residual 90 Sr, from its 90 Zr daughter, and from any remaining impurities by passing the sample through a final column designed to selectively retain yttrium.