|
|||||
|
|
Measurement and calculation of neutron densities in BWR high burn-up fuels |
|
| Authors: | Ryuichi Tayama Katsumi Hayashi a Ryo Iwasaki Masana Sasaki Yoshinori Etoh Hiroshi Sakurai |
| Affiliation: | a Hitachi Engineering Co., Ltd., Saiwai-cho, Hitachi-shi, Ibaraki-ken 317-0073, Japan b Hitachi Ltd., Saiwai-cho, Hitachi-shi, Ibaraki-ken 317-8511, Japan c Nuclear Power Engineering Corporation (NUPEC), Toranomon, Minato-ku, Tokyo 105-0001, Japan d Nippon Nuclear Fuel Development Co Ltd. (NFD), Oarai-machi, Ibaraki-ken 311-1313, Japan |
| Abstract: | A neutron-scanning device was developed for measuring accurate neutron densities of BWR high burn-up fuels up to 65 GWd tU?1. Characteristic test of this device was done with a 252Cf source and adopted to measure axial distributions of neutron densities of BWR spent fuels with various enrichments (2.0–3.4%), which had been irradiated up to 60 GWd tU?1 at Fukushima Daini Nuclear Power Station Unit 2(2F-2). We found the measured neutron densities were proportional to about fourth power of the corresponding burn-up values. The neutron densities calculated by the ORIGEN2.1 code and various cross section libraries showed good agreements with the measured ones in profile and absolute value except for BWR-UE file mainly based on ENDF/B-IV. The BS240J32 library based on JENDL3.2 was the best among the investigated libraries. |
| Keywords: | Neutron-scanning device Neutron densities BWR spent fuels Burn-up range 30-60GWd tU?1 Enrichment range 2 0–3 4% BF3 detector 252Cf standard source |
| 本文献已被 ScienceDirect 等数据库收录！ | |