Project/Area Number |
23360423
|
Research Category |
Grant-in-Aid for Scientific Research (B)
|
Allocation Type | Single-year Grants |
Section | 一般 |
Research Field |
Nuclear engineering
|
Research Institution | Nagaoka University of Technology (2012-2015) Tokyo Institute of Technology (2011) |
Principal Investigator |
Suzuki Tatsuya 長岡技術科学大学, 工学(系)研究科(研究院), 教授 (70323839)
|
Co-Investigator(Kenkyū-buntansha) |
NOGAMI Masanobu 近畿大学, 理工学部, 教授 (50415866)
NOMURA Masao 東京工業大学, 原子炉工学研究所, 助教 (60100997)
|
Co-Investigator(Renkei-kenkyūsha) |
ARAI Tsuyoshi 芝浦工業大学, 工学部, 准教授 (60415867)
KOYAMA Shin-ichi 独立行政法人日本原子力研究開発機構, 大洗研究開発センター, 副主任研究員 (70421782)
OHSAKA Masahiko 独立行政法人日本原子力研究開発機構, 大洗研究開発センター, 研究員 (10421471)
|
Research Collaborator |
TACHIBANA Yu 長岡技術科学大学, 大学院工学研究科, 助教 (40634928)
SATO Nobuhiro 京都大学, 原子炉実験所, 助教 (10303918)
KITAGAKI Toru
YAMASAKI Yuki
TOMOBUCHI Yusuke
KANESHIKI Toshitaka
HARATANI Tomohiro
NISHIDA Tetsuhiro
TAJIMA Shinya
ISHII Ryota
SAKAMOTO Hisanori
|
Project Period (FY) |
2011-04-01 – 2016-03-31
|
Project Status |
Completed (Fiscal Year 2015)
|
Budget Amount *help |
¥17,810,000 (Direct Cost: ¥13,700,000、Indirect Cost: ¥4,110,000)
Fiscal Year 2015: ¥2,990,000 (Direct Cost: ¥2,300,000、Indirect Cost: ¥690,000)
Fiscal Year 2014: ¥2,990,000 (Direct Cost: ¥2,300,000、Indirect Cost: ¥690,000)
Fiscal Year 2013: ¥4,030,000 (Direct Cost: ¥3,100,000、Indirect Cost: ¥930,000)
Fiscal Year 2012: ¥4,160,000 (Direct Cost: ¥3,200,000、Indirect Cost: ¥960,000)
Fiscal Year 2011: ¥3,640,000 (Direct Cost: ¥2,800,000、Indirect Cost: ¥840,000)
|
Keywords | 核燃料サイクル / 使用済み燃料 / 核種分離 / プラズマ化学 / 大気圧非平衡プラズマ / 固体抽出剤 / イオン交換 / 燃料再処理 / 放射能除染 / 固体抽出材 / クロマトグラフィ / 原子力エネルギー / 燃料サイクル / ピリジン樹脂 / クラウンエーテル樹脂 / イミノ二酢酸樹脂 / フェロシアン化物含浸吸着剤 |
Outline of Final Research Achievements |
Many kinds of elements are contained in the nuclear spent fuel. Some of them are valuable elements. Some of them constitute a limitation factor of the amount of high-level waste in vitrified waste and the emplacement area for high-level waste disposal. Thus, the separation of these elements is required. For the development of nuclide separation method from the spent fuel, the basic study on the atmospheric-pressure non-thermal plasma chemical conversion and the dissolution of spent fuel was carried out, novel solid-type extractants were developed and the nuclide separation using the developed extractants was investigated.
|