JP2013224488A - コリウムおよび使用済み核燃料の安定化処理方法 - Google Patents
コリウムおよび使用済み核燃料の安定化処理方法 Download PDFInfo
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Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/28—Selection of specific coolants ; Additions to the reactor coolants, e.g. against moderator corrosion
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/42—Reprocessing of irradiated fuel
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/42—Reprocessing of irradiated fuel
- G21C19/44—Reprocessing of irradiated fuel of irradiated solid fuel
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/42—Reprocessing of irradiated fuel
- G21C19/44—Reprocessing of irradiated fuel of irradiated solid fuel
- G21C19/46—Aqueous processes, e.g. by using organic extraction means, including the regeneration of these means
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/42—Reprocessing of irradiated fuel
- G21C19/44—Reprocessing of irradiated fuel of irradiated solid fuel
- G21C19/48—Non-aqueous processes
-
- 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
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
-
- 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
- Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
- Y02W30/00—Technologies for solid waste management
- Y02W30/50—Reuse, recycling or recovery technologies
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- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Electrolytic Production Of Metals (AREA)
Abstract
【解決手段】核物質を安定化させる方法は、電解還元装置の第1の溶融塩電解液内で核物質を電解還元させて還元物質を得ることを含むことができる。第1の溶融塩電解液内で、電解還元の副生成物として還元装置廃棄物が蓄積することができる。電解還元後、還元物質を電解精錬装置の第2の溶融塩電解液内で電解溶解させて、電解精錬装置の精錬装置カソードアセンブリ上で精製金属生成物を得ることができる。電解精錬の結果、第2の溶融塩電解液内で第1の精錬装置廃棄物が蓄積することができ、電解精錬装置の精錬装置アノードアセンブリ内で第2の精錬装置廃棄物が蓄積することができる。電解還元装置からの還元装置廃棄物および電解精錬装置からの第1の精錬装置廃棄物は、セラミックの廃棄物形態に変換することができ、電解精錬装置からの第2の精錬装置廃棄物は、金属の廃棄物形態に変換することができる。
【選択図】図1
Description
アノードアセンブリでは、酸化物イオンが酸素ガスに変換される。処理中は、それぞれのアノードアセンブリのアノードシュラウドを使用して、電解酸化物還元システムから酸素ガスを希釈、冷却、および除去することができる。このアノード反応は、次のように表すことができる。
金属酸化物は二酸化ウラン(UO2)とすることができ、還元生成物は金属ウランとすることができる。しかし、この電解酸化物還元システムでは、他のタイプの酸化物を対応する金属に還元させることもできることを理解されたい。同様に、電解酸化物還元システムで使用される溶融塩電解液は、特にこれに限定されるものではなく、還元させる酸化物供給物質に応じて変更することができる。
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Claims (20)
- 核物質を安定化させる方法であって、
第1の溶融塩電解液、および前記核物質を保持するように構成された還元装置カソードアセンブリを含む電解還元装置内へ、前記核物質を装入するステップと、
前記電解還元装置の前記第1の溶融塩電解液内で前記核物質を還元させて、前記還元装置カソードアセンブリ内で還元物質を得るステップと、
前記第1の溶融塩電解液内で還元装置廃棄物を蓄積させるステップと、
第2の溶融塩電解液、精錬装置カソードアセンブリ、および前記還元物質を保持するように構成された精錬装置アノードアセンブリを含む電解精錬装置内へ、前記還元物質を装入するステップと、
前記還元物質を前記電解精錬装置の前記第2の溶融塩電解液内で電解溶解させて、前記精錬装置カソードアセンブリ上で精製金属生成物を得るステップと、
前記第2の溶融塩電解液内で第1の精錬装置廃棄物を蓄積させ、前記精錬装置アノードアセンブリ内で第2の精錬装置廃棄物を蓄積させるステップとを含む方法。 - 前記核物質を装入する前記ステップが、前記電解還元装置内へコリウムを装入するステップを含む、請求項1記載の方法。
- 前記核物質を装入する前記ステップが、前記電解還元装置内へ使用済み核燃料を装入するステップを含む、請求項1記載の方法。
- 前記核物質を装入する前記ステップが、前記電解還元装置内へ酸化ウランを含む供給物質を装入するステップを含む、請求項1記載の方法。
- 前記核物質を装入する前記ステップが、前記電解還元装置内へ塩化ナトリウムを含む供給物質を装入するステップを含む、請求項1記載の方法。
- 前記電解還元装置内へ前記核物質を装入する前記ステップが、前記核物質および前記還元装置カソードアセンブリが水中にある間に、前記還元装置カソードアセンブリ内へ前記核物質を配置するステップを含む、請求項1記載の方法。
- 前記電解還元装置の前記第1の溶融塩電解液内で前記核物質を還元させる前に、前記還元装置カソードアセンブリを脱水するステップ
をさらに含む、請求項6記載の方法。 - 前記電解還元装置内へ前記核物質を装入する前記ステップが、前記核物質および前記還元装置カソードアセンブリが原子炉の既存のプール内に浸漬されている間に、前記還元装置カソードアセンブリ内へ前記核物質を配置するステップを含む、請求項1記載の方法。
- 前記第1の溶融塩電解液内で前記核物質を還元させる前記ステップが、塩化リチウムの溶融塩槽内に前記核物質を浸漬するステップを含む、請求項1記載の方法。
- 還元装置廃棄物を蓄積させる前記ステップが、第1族元素および第2族元素の少なくとも1つを含むハロゲン化合物を蓄積させるステップを伴う、請求項1記載の方法。
- 前記第2の溶融塩電解液内で前記還元物質を電解溶解する前記ステップが、塩化リチウムまたはLiCl−KCl共融混合物の溶融塩槽内に前記還元物質を浸漬するステップを含む、請求項1記載の方法。
- 第1の精錬装置廃棄物を蓄積させる前記ステップが、前記第2の溶融塩電解液内で超ウラン元素を含むハロゲン化合物を蓄積させるステップを伴う、請求項1記載の方法。
- 第2の精錬装置廃棄物を蓄積させる前記ステップが、前記精錬装置アノードアセンブリ内でジルコニウムおよび貴金属を蓄積させるステップを伴う、請求項1記載の方法。
- 前記電解還元装置内へ前記核物質を装入する前に、前記核物質を複数の断片に分割するステップ
をさらに含む、請求項1記載の方法。 - 前記核物質を分割する前記ステップが水中で実行される、請求項14記載の方法。
- 前記核物質を分割する前記ステップが、前記核物質が原子炉の既存のプール内に浸漬されている間に実行される、請求項14記載の方法。
- 前記電解還元装置からの前記還元装置廃棄物および前記電解精錬装置からの前記第1の精錬装置廃棄物をセラミックの廃棄物形態に変換するステップ
をさらに含む、請求項1記載の方法。 - セラミックの廃棄物形態に変換する前記ステップが、ガラス方ソーダ石を得るステップを含む、請求項17記載の方法。
- 前記電解精錬装置からの前記第2の精錬装置廃棄物を金属の廃棄物形態に変換するステップ
をさらに含む、請求項1記載の方法。 - 金属の廃棄物形態に変換する前記ステップが、金属インゴットを得るステップを含む、請求項19記載の方法。
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US13/453,290 US8968547B2 (en) | 2012-04-23 | 2012-04-23 | Method for corium and used nuclear fuel stabilization processing |
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RU2804570C1 (ru) * | 2022-03-30 | 2023-10-02 | Частное Учреждение По Обеспечению Научного Развития Атомной Отрасли "Наука И Инновации" (Частное Учреждение "Наука И Инновации") | Способ извлечения циркония из облученных циркониевых материалов для снижения объема высокоактивных радиоактивных отходов |
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US20130277228A1 (en) | 2013-10-24 |
KR20130119374A (ko) | 2013-10-31 |
EP2657942A1 (en) | 2013-10-30 |
JP5849064B2 (ja) | 2016-01-27 |
US8968547B2 (en) | 2015-03-03 |
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