Simple formula to evaluate helium production amount in fast reactor MA-containing MOX fuel and its accuracy |
| |
| Authors: | Hiroshi Akie Isamu Sato Motoe Suzuki Hiroyuki Serizawa Yasuo Arai |
| |
| Affiliation: | 1. Nuclear Science and Engineering Directorate, Japan Atomic Energy Agency, Tokai-mura , Ibaraki-ken , 319-1195 , Japan akie.hiroshi@jaea.go.jp;3. Advanced Nuclear System Research and Development Directorate, Japan Atomic Energy Agency, Oarai-machi, Ibaraki-ken, 311-1393, Japan;4. Nuclear Safety Research Center, Japan Atomic Energy Agency, Tokai-mura, Ibaraki-ken, 319-1195, Japan;5. Nuclear Science and Engineering Directorate, Japan Atomic Energy Agency, Tokai-mura , Ibaraki-ken , 319-1195 , Japan |
| |
| Abstract: | A simple formula is developed for the evaluation of the helium production amount in fast reactor minor actinide (MA) containing uranium–plutonium mixed oxide (MOX) fuel. For the subroutine use in the existing fuel behavior analysis code, the formula is designed putting emphasis on simplicity and quickness rather than accuracy. The accuracy of the formula is confirmed by comparing with the detailed calculation with SWAT code, and also with the post irradiation examination (PIE) results of the fuel pin irradiated at the experimental fast reactor JOYO. As a result, it is found that the formula evaluates the helium production amount with the difference of less than about 10% from the detailed calculation and the PIE results, when the MA isotope content is less than 5 wt.%. Based on these results, the formula is installed in the fuel behavior analysis code for the simulation of helium behavior in fast reactor fuels. |
| |
| Keywords: | nuclear fuel minor actinides helium behavior helium production formula SWAT code JOYO reactor fuel behavior analysis code |
|
|
