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遮蔽型イオンマイクロアナライザ(SIMA)による燃焼度測定技術の開発
| Title: | 遮蔽型イオンマイクロアナライザ(SIMA)による燃焼度測定技術の開発 |
| Other Titles: | Development of new method for burnup measurement using shielded ion microprobe analyzer (SIMA) |
| Authors: | 鵜飼, 重治1 Browse this author | | 吽野, 一郎2 Browse this author | | 櫛田, 尚也3 Browse this author | | 水野, 峰雄4 Browse this author | | 榎戸, 裕二5 Browse this author |
| Authors(alt): | Ukai, Shigeharu1 | | Unno, Ichiro2 | | Kushida, Naoya3 | | Mizuno, Mineo4 | | Enokido, Yuji5 |
| Keywords: | accuracy | | burnup | | IMA | | measuring methods | | neodymium isotopes | | plutonium isotopes | | shielded ion microprobe analyzer | | spent fuel elements | | thermal neutron depression | | uranium isotopes |
| Issue Date: | 30-Jun-1987 |
| Publisher: | 日本原子力学会 |
| Journal Title: | 日本原子力学会誌 |
| Journal Title(alt): | Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan |
| Volume: | 29 |
| Issue: | 6 |
| Start Page: | 528 |
| End Page: | 537 |
| Publisher DOI: | 10.3327/jaesj.29.528 |
| Abstract: | A new method of the fuel burnup measurement using a shielded ion microprobe analyzer (SIMA) has been developed. This method is based on the direct isotope analysis of U, Pu and Nd in an irradiated fuel by means of the secondary ion mass spectrometry. The sample tests on the irradiated fuels up to 13a/0 burnup have shown an accuracy within 6%.
While the conventional isotope dilution method requires the acid-dissolution and the chemical separation of the irradiated fuel by handling samples in a glovebox, the new method can measure the burnup on a fuel in shielded apparatus remotely and directly. Consequently, the time for measurement was reduced to about one tenth of that of the conventional method, and a human radiation exposure became negligible.
A microarea surface analysis by the SIMA provides the local burnup distribution in small area. Using this technique, the radial profile of the burnup distribution due to a thermal neutron depression was obtained in the fuel pellet irradiated in JRR-2 reactor. The radial burnup distribution was also measured in the mixed-oxide fuel pellet of the experimental fast reactor "JOYO" MK-II, which revealed some effects of Pu redistribution on the radial burnup profile. |
| Type: | article |
| URI: | http://hdl.handle.net/2115/76312 |
| Appears in Collections: | 工学院・工学研究院 (Graduate School of Engineering / Faculty of Engineering) > 雑誌発表論文等 (Peer-reviewed Journal Articles, etc)
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