JP2019101008A - Spent nuclear fuel detoxification facility - Google Patents
Spent nuclear fuel detoxification facility Download PDFInfo
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- JP2019101008A JP2019101008A JP2017243212A JP2017243212A JP2019101008A JP 2019101008 A JP2019101008 A JP 2019101008A JP 2017243212 A JP2017243212 A JP 2017243212A JP 2017243212 A JP2017243212 A JP 2017243212A JP 2019101008 A JP2019101008 A JP 2019101008A
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- JP
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- Prior art keywords
- hydrogen
- oxygen
- spent nuclear
- nuclear fuel
- fuel
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- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E60/00—Enabling technologies; Technologies with a potential or indirect contribution to GHG emissions mitigation
- Y02E60/30—Hydrogen technology
- Y02E60/50—Fuel cells
Abstract
Description
本発明は使用済み核燃料を無害化に関する The present invention relates to the detoxification of spent nuclear fuel
放射性廃棄物は地下埋設しかなく、汚染水は希釈して、海に放流する位しかなく、ただタンクに貯蔵し処理に苦慮している。これを廃棄物類を燃料にして、電力を起こして、電気分解し、無害化して処理する。 Radioactive waste is only buried underground, contaminated water is diluted and only released to the sea, and it is difficult to store it in a tank and treat it. The waste is used as fuel, electricity is generated, electrolyzed, detoxified and treated.
放射性廃棄物発電装置より From radioactive waste generator
使用済み核燃料の処理 Processing of spent nuclear fuel
放射性廃棄物発電装置により、電力を生み、そのコストの掛からない電力で、汚染水を電気分解しH2水素とO2酸素を生み、水素は燃料電池の水素エネルギーへ、酸素は自然に放出して、環境保全へ、トリチウムだけが残るが、これはβ崩壊するので、放射性廃棄物発電装置で電気エネルギーに変換し半減期を待ち安定元素へとなる。 The radioactive waste power generator produces electric power, and the inexpensive electric power electrolyzes the polluted water to generate H2 hydrogen and O2 oxygen, which is released to the hydrogen energy of the fuel cell and oxygen is released naturally. For environmental protection, only tritium remains, but this is β-decayed, so it is converted to electrical energy by the radioactive waste power generator, and it has a half-life to become a stable element.
使用済み核燃料だけで処理し、無害化をし、水素エネルギーのコスト問題にも貢献し、環境保全にもなる。 It treats only with spent nuclear fuel, makes it harmless, contributes to the cost problem of hydrogen energy, and also protects the environment.
放射性廃棄物発電装置を使って電力を低コストで得て、汚染水を電気分解し、水素と酸素得て、水素エネルギーの燃料とし、酸素は環境保全へ、トリチウムが残るのでこれは放射性廃棄物発電装置で電力を得て、半減期を待ち安定元素へと Using radioactive waste generators to obtain electricity at low cost, electrolyze polluted water, obtaining hydrogen and oxygen, fueling hydrogen energy, oxygen for environmental protection, tritium remains, which is a radioactive waste Obtain power with the power generator, wait for half life and turn into stable element
使用済み核燃料の処理に寄与し、未来エネルギーの水素エネルギー産業へ、低コストで寄与する。最終的に残るトリチウムも弱いβ崩壊するので集めて、放射性廃棄物発電装置で電力を得て、無害化まで、半減期を待ち核変により安定元素へとなる事を期待する。 Contributing to the processing of spent nuclear fuel and contributing to the future energy hydrogen energy industry at low cost. Finally, tritium which remains finally is also collected as it is weakly β-decayed, and it is expected that power will be obtained by the radioactive waste power generator, and it will turn into a stable element by changing its half-life into a decaying nucleus until harmless.
Claims (1)
使用済み核燃料を放射性廃棄物発電装置にて発電しながら、100年・200年単位で半減期を待ち、その原子力発電よりの廃棄物だけを原料として燃料と電力を生み、廃棄物を処理する設備です。The radioactive waste power generator obtains electric power from the spent nuclear fuel, electrolyzes the polluted water, decomposes it into H2 hydrogen and O2 oxygen, collects tritium, uses it as a raw material, and uses the radioactive waste power generator to generate electric power obtain. H2 hydrogen is supplied to the fuel cell, and O2 oxygen is released naturally, and it is treated as clean as if it were photosynthesized.
A facility that consumes spent nuclear fuel with a radioactive waste power generator, waits for a half life in units of 100 or 200 years, produces fuel and electricity using only waste from that nuclear power generation, and processes waste is.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
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JP2017243212A JP2019101008A (en) | 2017-12-01 | 2017-12-01 | Spent nuclear fuel detoxification facility |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
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JP2017243212A JP2019101008A (en) | 2017-12-01 | 2017-12-01 | Spent nuclear fuel detoxification facility |
Publications (1)
Publication Number | Publication Date |
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JP2019101008A true JP2019101008A (en) | 2019-06-24 |
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ID=66976783
Family Applications (1)
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JP2017243212A Pending JP2019101008A (en) | 2017-12-01 | 2017-12-01 | Spent nuclear fuel detoxification facility |
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JP (1) | JP2019101008A (en) |
Citations (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2015021877A (en) * | 2013-07-22 | 2015-02-02 | 矢内 誠 | Radioactive material removal device and method for solidifying radioactive contaminated water |
US20150310952A1 (en) * | 2014-02-17 | 2015-10-29 | City Labs, Inc. | Tritium Direct Conversion Semiconductor Device for Use With Gallium Arsenide or Germanium Sustrates |
JP2016075689A (en) * | 2013-05-01 | 2016-05-12 | 竹田 眞司 | Radioactive waste treatment, and removal method of radioactive contamination material |
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2017
- 2017-12-01 JP JP2017243212A patent/JP2019101008A/en active Pending
Patent Citations (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2016075689A (en) * | 2013-05-01 | 2016-05-12 | 竹田 眞司 | Radioactive waste treatment, and removal method of radioactive contamination material |
JP2015021877A (en) * | 2013-07-22 | 2015-02-02 | 矢内 誠 | Radioactive material removal device and method for solidifying radioactive contaminated water |
US20150310952A1 (en) * | 2014-02-17 | 2015-10-29 | City Labs, Inc. | Tritium Direct Conversion Semiconductor Device for Use With Gallium Arsenide or Germanium Sustrates |
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