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.
89Sr production in fast reactors
ConclusionsIn summary, we have proposed a new method for producing89Sr for medical purposes from natural yttrium according to the reaction (n, p) in fast-neutron reactors. Investigations confirm the computational parameters of the production: from 2 to 15 mCi89Sr per gram of the starting yttrium. We have shown that90Sr can be extracted and the final product with the required radionuclide purity can be obtained. Commercial production of89Sr in BR-10 and BOR-60 has now started.
Analysis and Results of a Hydrogen-Moderated Isotope Production Assembly in the Fast Flux Test Facility
This paper reports on a cobalt test assembly containing yttrium hydride pins for neutron moderation irradiated in the Fast Flux Test Facility (FFTF) during cycle 9A for 137.7 equivalent full-power days at a power level of 291 MW. The 36 test pins consisted of a batch of 32 pins containing cobalt metal used to produce {sup 60}Co and a set of four pins with europium oxide to produce {sup 153}Gd, a radioisotope used in detection of the bone disease osteoporosis. Postirradiation examination of the cobalt pins determined the {sup 60}Co production to be predictable to an accuracy of {approximately} 5%. The measured {sup 60}Co spatially distributed concentrations were within 20% of the calculated concentrations. The assembly average {sup 60}Co measured activity was 4% less than the calculated value. The europium oxide pins were gamma scanned for the europium isotopes {sup 152}Eu and {sup 154}Eu to an absolute accuracy of {approx equal} 10%. The measured europium radioisotope and {sup 153}Gd concentrations were within 20% of calculated values. The hydride assembly performed well and is an excellent vehicle for many FFTF isotope production applications. The results also demonstrate the accuracy of the calculational methods developed by the Westinghouse Hanford Company for predictingmore » isotope production rates in this type of assembly.« less