Treatment of fuel debris by selective fluorination and molten salt electrolysis
Project/Area Number |
25630429
|
Research Category |
Grant-in-Aid for Challenging Exploratory Research
|
Allocation Type | Multi-year Fund |
Research Field |
Nuclear engineering
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Research Institution | Tokyo Institute of Technology |
Principal Investigator |
|
Co-Investigator(Renkei-kenkyūsha) |
SATO Nobuaki 東北大学, 多元物質科学研究所, 教授 (70154078)
|
Project Period (FY) |
2013-04-01 – 2015-03-31
|
Project Status |
Completed (Fiscal Year 2014)
|
Budget Amount *help |
¥3,900,000 (Direct Cost: ¥3,000,000、Indirect Cost: ¥900,000)
Fiscal Year 2014: ¥1,950,000 (Direct Cost: ¥1,500,000、Indirect Cost: ¥450,000)
Fiscal Year 2013: ¥1,950,000 (Direct Cost: ¥1,500,000、Indirect Cost: ¥450,000)
|
Keywords | 燃料デブリ / 選択フッ化 / 溶融塩電解 / 酸化ウラン / 酸化ジルコニウム / 固溶体 / 原子力学 / 選択溶解 |
Outline of Final Research Achievements |
For stabilization of fuel debris at Fukushima Daiichi power plant accident, basic experiments of selective fluorination and molten salt electrolysis have been performed. To separate between uranium and zirconium without vaporization of uranium by fluorination, solid solution should be fluorinated by hydrogen fluoride gas at less than 400 oC, so that uranium would be selectively fluorinated into uranium tetrafluoride. And then, uranium can be dissolved into molten fluoride salt and electroreduced by electrolysis. To avoid fluorination of zirconium, pre-treatment of hydrogen reduction is not suitable. Even pre-treatment of oxidation would be effective to avoid zirconium fluoride vaporization at higher temperature.
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Report
(3 results)
Research Products
(6 results)