FR2901627B1 - Procede de retraitement d'un combustible nucleaire use et de preparation d'un oxyde mixte d'uranium et de plutonium - Google Patents
Procede de retraitement d'un combustible nucleaire use et de preparation d'un oxyde mixte d'uranium et de plutoniumInfo
- Publication number
- FR2901627B1 FR2901627B1 FR0604717A FR0604717A FR2901627B1 FR 2901627 B1 FR2901627 B1 FR 2901627B1 FR 0604717 A FR0604717 A FR 0604717A FR 0604717 A FR0604717 A FR 0604717A FR 2901627 B1 FR2901627 B1 FR 2901627B1
- Authority
- FR
- France
- Prior art keywords
- uranium
- plutonium
- aqueous
- nuclear fuel
- mixed oxide
- Prior art date
- 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.)
- Expired - Fee Related
Links
- 229910052770 Uranium Inorganic materials 0.000 title abstract 17
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 title abstract 17
- 229910052778 Plutonium Inorganic materials 0.000 title abstract 16
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 title abstract 16
- 238000000034 method Methods 0.000 title abstract 3
- 238000002360 preparation method Methods 0.000 title abstract 3
- 239000003758 nuclear fuel Substances 0.000 title 1
- 239000008346 aqueous phase Substances 0.000 abstract 6
- 239000002915 spent fuel radioactive waste Substances 0.000 abstract 4
- 238000000926 separation method Methods 0.000 abstract 3
- 239000000243 solution Substances 0.000 abstract 3
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 abstract 2
- 238000006243 chemical reaction Methods 0.000 abstract 2
- 230000004992 fission Effects 0.000 abstract 2
- 229910017604 nitric acid Inorganic materials 0.000 abstract 2
- 238000000746 purification Methods 0.000 abstract 2
- 238000004064 recycling Methods 0.000 abstract 2
- 229910052695 Americium Inorganic materials 0.000 abstract 1
- 229910052685 Curium Inorganic materials 0.000 abstract 1
- IYQHAABWBDVIEE-UHFFFAOYSA-N [Pu+4] Chemical compound [Pu+4] IYQHAABWBDVIEE-UHFFFAOYSA-N 0.000 abstract 1
- LXQXZNRPTYVCNG-UHFFFAOYSA-N americium atom Chemical compound [Am] LXQXZNRPTYVCNG-UHFFFAOYSA-N 0.000 abstract 1
- 239000007864 aqueous solution Substances 0.000 abstract 1
- 239000003795 chemical substances by application Substances 0.000 abstract 1
- 238000000658 coextraction Methods 0.000 abstract 1
- NIWWFAAXEMMFMS-UHFFFAOYSA-N curium atom Chemical compound [Cm] NIWWFAAXEMMFMS-UHFFFAOYSA-N 0.000 abstract 1
- 239000003085 diluting agent Substances 0.000 abstract 1
- 230000003647 oxidation Effects 0.000 abstract 1
- 238000007254 oxidation reaction Methods 0.000 abstract 1
- 239000012071 phase Substances 0.000 abstract 1
- 239000002904 solvent Substances 0.000 abstract 1
- AAORDHMTTHGXCV-UHFFFAOYSA-N uranium(6+) Chemical compound [U+6] AAORDHMTTHGXCV-UHFFFAOYSA-N 0.000 abstract 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract 1
Classifications
-
- 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
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
- C01G43/00—Compounds of uranium
- C01G43/003—Preparation involving a liquid-liquid extraction, an adsorption or an ion-exchange
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
- C01G43/00—Compounds of uranium
- C01G43/01—Oxides; Hydroxides
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
- C01G56/00—Compounds of transuranic elements
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
- C01G56/00—Compounds of transuranic elements
- C01G56/001—Preparation involving a liquid-liquid extraction, an adsorption or an ion-exchange
-
- 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
Landscapes
- Chemical & Material Sciences (AREA)
- Organic Chemistry (AREA)
- Inorganic Chemistry (AREA)
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Geology (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
- Extraction Or Liquid Replacement (AREA)
- Oxygen, Ozone, And Oxides In General (AREA)
Priority Applications (13)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR0604717A FR2901627B1 (fr) | 2006-05-24 | 2006-05-24 | Procede de retraitement d'un combustible nucleaire use et de preparation d'un oxyde mixte d'uranium et de plutonium |
DE200760003013 DE602007003013D1 (de) | 2006-05-24 | 2007-05-23 | Verfahren zur wiederaufbereitung von verbrauchtem kernbrennstoff und zur herstellung eines gemischten uran-plutonium-oxids |
PCT/EP2007/055024 WO2007135178A1 (fr) | 2006-05-24 | 2007-05-23 | Procédé de retraitement d'un combustible nucléaire épuisé et de préparation d'un oxyde mélangé d'uranium-plutonium |
CN2007800188112A CN101449338B (zh) | 2006-05-24 | 2007-05-23 | 用于后处理废核燃料及制备混合的铀-钚氧化物的方法 |
EP20070729457 EP2022061B1 (fr) | 2006-05-24 | 2007-05-23 | Procédé de retraitement d'un combustible nucléaire épuisé et de préparation d'un oxyde mélangé d'uranium-plutonium |
US12/300,705 US20090184298A1 (en) | 2006-05-24 | 2007-05-23 | Process for reprocessing a spent nuclear fuel and of preparing a mixed uranium-plutonium oxide |
ES07729457T ES2334852T3 (es) | 2006-05-24 | 2007-05-23 | Proceso para el reprocesamiento de un combustible nuclear agotado y de preparacion de un oxido mixto de uranio-plutonio. |
AT07729457T ATE447231T1 (de) | 2006-05-24 | 2007-05-23 | Verfahren zur wiederaufbereitung von verbrauchtem kernbrennstoff und zur herstellung eines gemischten uran-plutonium-oxids |
KR1020087028715A KR101386696B1 (ko) | 2006-05-24 | 2007-05-23 | 사용후 핵연료 재처리 및 우라늄-플루토늄 혼합 산화물 제조 방법 |
JP2009511522A JP5325098B2 (ja) | 2006-05-24 | 2007-05-23 | 使用済み核燃料を再処理しウラン・プルトニウム混合酸化物を調製する方法 |
RU2008151145A RU2431896C2 (ru) | 2006-05-24 | 2007-05-23 | Способ регенерации отработанного ядерного топлива и получения смешанного уран-плутониевого оксида |
US11/753,182 US7887767B2 (en) | 2006-05-24 | 2007-05-24 | Process for reprocessing a spent nuclear fuel and of preparing a mixed uranium-plutonium oxide |
ZA200809415A ZA200809415B (en) | 2006-05-24 | 2008-11-04 | Process for reprocessing a spent nuclear fuel and of preparing a mixed uranium-plutonium oxide |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR0604717A FR2901627B1 (fr) | 2006-05-24 | 2006-05-24 | Procede de retraitement d'un combustible nucleaire use et de preparation d'un oxyde mixte d'uranium et de plutonium |
Publications (2)
Publication Number | Publication Date |
---|---|
FR2901627A1 FR2901627A1 (fr) | 2007-11-30 |
FR2901627B1 true FR2901627B1 (fr) | 2009-05-01 |
Family
ID=37892451
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
FR0604717A Expired - Fee Related FR2901627B1 (fr) | 2006-05-24 | 2006-05-24 | Procede de retraitement d'un combustible nucleaire use et de preparation d'un oxyde mixte d'uranium et de plutonium |
Country Status (12)
Country | Link |
---|---|
US (2) | US20090184298A1 (fr) |
EP (1) | EP2022061B1 (fr) |
JP (1) | JP5325098B2 (fr) |
KR (1) | KR101386696B1 (fr) |
CN (1) | CN101449338B (fr) |
AT (1) | ATE447231T1 (fr) |
DE (1) | DE602007003013D1 (fr) |
ES (1) | ES2334852T3 (fr) |
FR (1) | FR2901627B1 (fr) |
RU (1) | RU2431896C2 (fr) |
WO (1) | WO2007135178A1 (fr) |
ZA (1) | ZA200809415B (fr) |
Families Citing this family (51)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2901627B1 (fr) * | 2006-05-24 | 2009-05-01 | Commissariat Energie Atomique | Procede de retraitement d'un combustible nucleaire use et de preparation d'un oxyde mixte d'uranium et de plutonium |
JP5193687B2 (ja) * | 2008-05-30 | 2013-05-08 | 株式会社東芝 | 使用済み燃料再処理方法 |
US8475747B1 (en) * | 2008-06-13 | 2013-07-02 | U.S. Department Of Energy | Processing fissile material mixtures containing zirconium and/or carbon |
JP5132476B2 (ja) * | 2008-08-12 | 2013-01-30 | 株式会社東芝 | 使用済核燃料の再処理方法および遠心抽出装置 |
US8571167B2 (en) * | 2009-06-01 | 2013-10-29 | Advanced Reactor Concepts LLC | Particulate metal fuels used in power generation, recycling systems, and small modular reactors |
FR2947663B1 (fr) | 2009-07-02 | 2011-07-29 | Areva Nc | Procede ameliore de traitement de combustibles nucleaires uses |
FR2948385B1 (fr) | 2009-07-27 | 2011-09-23 | Commissariat Energie Atomique | Procede de recuperation selective de l'americium a partir d'une phase aqueuse nitrique |
FR2948384B1 (fr) | 2009-07-27 | 2011-09-23 | Commissariat Energie Atomique | Augmentation du facteur de separation entre l'americium et le curium et/ou entre des lanthanides dans une operation d'extraction liquide-liquide |
FR2954354B1 (fr) * | 2009-12-22 | 2012-01-13 | Commissariat Energie Atomique | Procede de purification de l'uranium d'un concentre d'uranium naturel |
WO2011088116A1 (fr) | 2010-01-13 | 2011-07-21 | Advanced Reactor Concepts LLC | Combustible nucléaire en métal annulaire chemisé |
JP6001457B2 (ja) | 2010-02-22 | 2016-10-05 | アドバンスト・リアクター・コンセプツ・エルエルシー | 長い燃料交換間隔を有する小型の高速中性子スペクトル原子力発電所の高速中性子スペクトル原子炉システム、原子力を提供する方法、及び、炉心の締め付けのためのシステム |
US8741237B1 (en) * | 2010-04-12 | 2014-06-03 | U.S. Department Of Energy | Solvent extraction system for plutonium colloids and other oxide nano-particles |
FR2960690B1 (fr) * | 2010-05-27 | 2012-06-29 | Commissariat Energie Atomique | Procede de traitement de combustibles nucleaires uses ne necessitant pas d'operation de desextraction reductrice du plutonium |
RU2456244C2 (ru) * | 2010-08-30 | 2012-07-20 | Федеральное государственное унитарное предприятие "Производственное объединение "Маяк" | Способ переработки отработанных стекловолокнистых аэрозольных фильтров |
FR2968014B1 (fr) | 2010-11-25 | 2012-12-28 | Commissariat Energie Atomique | Procede de separation de l'americium des autres elements metalliques presents dans une phase aqueuse acide ou organique et ses applications |
JP5737931B2 (ja) * | 2010-12-24 | 2015-06-17 | 三菱重工業株式会社 | 抽出装置および使用済核燃料の再処理施設 |
JP5758209B2 (ja) * | 2011-06-14 | 2015-08-05 | 株式会社東芝 | 使用済み燃料再処理方法 |
JP5784476B2 (ja) * | 2011-12-09 | 2015-09-24 | 株式会社東芝 | ウランの回収方法 |
RU2502142C1 (ru) * | 2012-04-19 | 2013-12-20 | Федеральное государственное унитарное предприятие "Научно-исследовательский институт Научно-производственное объединение "ЛУЧ" (ФГУП "НИИ НПО "ЛУЧ") | Способ переработки уран-молибденовой композиции |
RU2537013C2 (ru) * | 2012-12-07 | 2014-12-27 | Открытое акционерное общество "Радиевый институт имени В.Г. Хлопина" | Топливная композиция для водоохлаждаемых реакторов аэс на тепловых нейтронах |
CN103305702B (zh) * | 2013-07-08 | 2014-12-24 | 中国原子能科学研究院 | 一种从Purex流程的2AW+2DW中放废液中回收和纯化镎的工艺 |
FR3015760B1 (fr) * | 2013-12-20 | 2016-01-29 | Commissariat Energie Atomique | Procede de traitement d'un combustible nucleaire use comprenant une etape de decontamination de l'uranium(vi) en au moins un actinide(iv) par complexation de cet actinide(iv) |
GB2538687B (en) * | 2014-04-14 | 2020-12-30 | Advanced Reactor Concepts LLC | Ceramic nuclear fuel dispersed in a metallic alloy matrix |
RU2561508C1 (ru) * | 2014-04-29 | 2015-08-27 | Федеральное государственное унитарное предприятие "Научно-исследовательский технологический институт имени А.П. Александрова" | Способ иммобилизации стронций-цезиевой фракции высокоактивных отходов включением в геокерамические матрицы |
CN104407062A (zh) * | 2014-09-11 | 2015-03-11 | 上海大学 | 一种快速分析磷酸三异戊酯的方法 |
JP6479398B2 (ja) * | 2014-10-10 | 2019-03-06 | 三菱重工業株式会社 | 再処理施設 |
FR3039547B1 (fr) | 2015-07-29 | 2017-08-25 | Areva Nc | Nouveaux n,n-dialkylamides dissymetriques, leur synthese et leurs utilisations |
FR3039696B1 (fr) | 2015-07-29 | 2017-07-28 | Commissariat Energie Atomique | Procede de traitement en un cycle, exempt d'operation de desextraction reductrice du plutonium, d'une solution aqueuse nitrique de dissolution d'un combustible nucleaire use |
FR3042903B1 (fr) * | 2015-10-21 | 2017-12-08 | Commissariat Energie Atomique | Utilisation d'acides hydroxyiminoalcanoiques comme agents anti-nitreux dans des operations de desextraction reductrice du plutonium |
CN106119578B (zh) * | 2016-06-27 | 2018-10-09 | 中国原子能科学研究院 | 一种草酸钚沉淀母液中硝酸-草酸浓缩与破坏的一体化方法 |
CN107845433B (zh) * | 2016-09-20 | 2019-09-17 | 中核四〇四有限公司 | 一种mox粉末成形剂与润滑剂添加方法 |
CN107845432B (zh) * | 2016-09-20 | 2019-09-17 | 中核四〇四有限公司 | 一种mox球磨粉末混料方法 |
JP6896561B2 (ja) | 2016-09-26 | 2021-06-30 | 株式会社東芝 | 軽水炉用燃料集合体、軽水炉炉心、軽水炉用燃料集合体製造方法およびmox燃料集合体製造方法 |
CN107610796B (zh) * | 2017-08-29 | 2019-08-13 | 中核四0四有限公司 | Mox制备过程不合格粉末回收方法 |
WO2019115394A1 (fr) | 2017-12-11 | 2019-06-20 | Orano Cycle | Procédé de préparation d'une poudre comprenant des particules d'octaoxyde de triuranium et de particules de dioxyde de plutonium |
FR3074794B1 (fr) | 2017-12-11 | 2020-01-10 | Areva Nc | Procede de preparation d'une poudre comprenant des particules de sesquioxyde d'uranium et des particules de dioxyde de plutonium |
CN108267347A (zh) * | 2017-12-27 | 2018-07-10 | 中核四0四有限公司 | 一种采用tbp萃取剂测定mox芯块中银杂质含量的方法 |
CN108630332B (zh) * | 2018-03-26 | 2021-06-18 | 中国核电工程有限公司 | 一种草酸盐沉淀过滤母液中草酸根的破坏装置及破坏方法 |
CN109234534B (zh) * | 2018-08-08 | 2019-11-08 | 中国原子能科学研究院 | 一种从高放废液中共萃取三价锕系和三价镧系元素的工艺 |
CN109402413B (zh) * | 2018-10-30 | 2020-11-03 | 中国工程物理研究院核物理与化学研究所 | 一种乏燃料元件裂变产物中钯的回收方法 |
CN109735859B (zh) * | 2019-03-18 | 2020-10-09 | 中国原子能科学研究院 | 一种3-戊基肼及其盐的用途 |
CN112309601B (zh) * | 2019-07-26 | 2023-04-11 | 中国科学院大连化学物理研究所 | 一种稀释剂及其制备和应用 |
KR102293451B1 (ko) * | 2019-11-08 | 2021-08-25 | 한국원자력연구원 | 금속연료 폐기물을 이용한 금속연료심 제조방법 및 이 방법에 의해 제조된 금속연료심 |
CN112940781B (zh) * | 2019-12-10 | 2022-10-25 | 中国科学院大连化学物理研究所 | 一种稀释剂和其制备与应用 |
CN112941346A (zh) * | 2019-12-10 | 2021-06-11 | 中国科学院大连化学物理研究所 | 一种稀释剂及其制备和应用 |
RU2727140C1 (ru) * | 2020-01-28 | 2020-07-21 | Федеральное государственное унитарное предприятие "Горно-химический комбинат" (ФГУП "ГХК") | Способ экстракционной переработки облученного ядерного топлива |
CN111863303B (zh) * | 2020-06-10 | 2022-08-05 | 中国原子能科学研究院 | 一种purex流程含钚团聚物的溶解与回收方法 |
CN113512653A (zh) * | 2021-06-16 | 2021-10-19 | 中国原子能科学研究院 | 一种从辐照镎靶中提取钚-238的方法 |
CN113241208B (zh) * | 2021-06-22 | 2024-05-14 | 中国原子能科学研究院 | 用于钚尾端处理的容纳装置、蒸发煅烧系统及方法 |
FR3139408B1 (fr) | 2022-09-02 | 2024-09-13 | Commissariat Energie Atomique | Procédé de désextraction d’uranium(vi) et d’un actinide(iv) d’une solution organique par précipitation oxalique |
WO2024238826A1 (fr) * | 2023-05-16 | 2024-11-21 | Shine Technologies, Llc | Procédés et systèmes de partitionnement, de transmutation et de recyclage de combustible nucléaire usagé |
Family Cites Families (11)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
NL301862A (fr) * | 1962-12-26 | 1900-01-01 | ||
GB2004407B (en) * | 1977-09-16 | 1982-03-03 | British Nuclear Fuels Ltd | Purification of plutonium |
DE2838541A1 (de) * | 1977-09-16 | 1979-04-05 | British Nuclear Fuels Ltd | Verfahren zur reinigung einer plutonium enthaltenden phase |
US4278559A (en) * | 1978-02-16 | 1981-07-14 | Electric Power Research Institute | Method for processing spent nuclear reactor fuel |
FR2607823B1 (fr) * | 1986-12-03 | 1989-02-17 | Commissariat Energie Atomique | Procede pour separer le technetium present dans un solvant organique avec du zirconium et au moins un autre metal tel que l'uranium ou le plutonium, utilisable notamment pour le retraitement des combustibles nucleaires irradies |
GB9722930D0 (en) * | 1997-10-31 | 1998-01-07 | British Nuclear Fuels Plc | Nuclear fuel reprocessing |
GB9802852D0 (en) * | 1998-02-11 | 1998-04-08 | British Nuclear Fuels Plc | Nuclear fuel reprocessing |
FR2815035B1 (fr) * | 2000-10-05 | 2003-03-07 | Commissariat Energie Atomique | Procede de coprecipitation d'actinides et procede de preparation d'oxydes mixtes d'actinides |
CN1182543C (zh) * | 2003-04-04 | 2004-12-29 | 清华大学 | 一种乏燃料后端处理一体化的方法 |
FR2870841B1 (fr) * | 2004-05-28 | 2007-02-09 | Commissariat Energie Atomique | Procede de coprecipitation d'actinides a des etats d'oxydation distincts et procede de preparation de composes mixtes d'actinides |
FR2901627B1 (fr) * | 2006-05-24 | 2009-05-01 | Commissariat Energie Atomique | Procede de retraitement d'un combustible nucleaire use et de preparation d'un oxyde mixte d'uranium et de plutonium |
-
2006
- 2006-05-24 FR FR0604717A patent/FR2901627B1/fr not_active Expired - Fee Related
-
2007
- 2007-05-23 US US12/300,705 patent/US20090184298A1/en not_active Abandoned
- 2007-05-23 EP EP20070729457 patent/EP2022061B1/fr active Active
- 2007-05-23 KR KR1020087028715A patent/KR101386696B1/ko not_active Expired - Fee Related
- 2007-05-23 RU RU2008151145A patent/RU2431896C2/ru active
- 2007-05-23 DE DE200760003013 patent/DE602007003013D1/de active Active
- 2007-05-23 CN CN2007800188112A patent/CN101449338B/zh active Active
- 2007-05-23 ES ES07729457T patent/ES2334852T3/es active Active
- 2007-05-23 JP JP2009511522A patent/JP5325098B2/ja active Active
- 2007-05-23 AT AT07729457T patent/ATE447231T1/de not_active IP Right Cessation
- 2007-05-23 WO PCT/EP2007/055024 patent/WO2007135178A1/fr active Application Filing
- 2007-05-24 US US11/753,182 patent/US7887767B2/en active Active
-
2008
- 2008-11-04 ZA ZA200809415A patent/ZA200809415B/xx unknown
Also Published As
Publication number | Publication date |
---|---|
KR20090010217A (ko) | 2009-01-29 |
RU2431896C2 (ru) | 2011-10-20 |
KR101386696B1 (ko) | 2014-04-18 |
RU2008151145A (ru) | 2010-06-27 |
US7887767B2 (en) | 2011-02-15 |
ATE447231T1 (de) | 2009-11-15 |
DE602007003013D1 (de) | 2009-12-10 |
CN101449338B (zh) | 2012-10-24 |
FR2901627A1 (fr) | 2007-11-30 |
EP2022061A1 (fr) | 2009-02-11 |
EP2022061B1 (fr) | 2009-10-28 |
US20070290178A1 (en) | 2007-12-20 |
US20090184298A1 (en) | 2009-07-23 |
JP5325098B2 (ja) | 2013-10-23 |
ZA200809415B (en) | 2009-10-28 |
JP2009537838A (ja) | 2009-10-29 |
ES2334852T3 (es) | 2010-03-16 |
CN101449338A (zh) | 2009-06-03 |
WO2007135178A1 (fr) | 2007-11-29 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
FR2901627B1 (fr) | Procede de retraitement d'un combustible nucleaire use et de preparation d'un oxyde mixte d'uranium et de plutonium | |
Magnusson et al. | Demonstration of a TODGA based extraction process for the partitioning of minor actinides from a PUREX raffinate: part III: centrifugal contactor run using genuine fuel solution | |
Wilden et al. | Laboratory-scale counter-current centrifugal contactor demonstration of an innovative-SANEX process using a water soluble BTP | |
Hill et al. | SANEX-BTP process development studies | |
FR2907346B1 (fr) | Separation groupee des actinides a partir d'une phase aqueuse fortement acide, utilisant un extractant solvatant en milieu relargant. | |
Serrano-Purroy et al. | First demonstration of a centrifugal solvent extraction process for minor actinides from a concentrated spent fuel solution | |
FR2880180B1 (fr) | Perfectionnement du procede purex et ses utilisations | |
FR2947663B1 (fr) | Procede ameliore de traitement de combustibles nucleaires uses | |
JP2008525812A5 (fr) | ||
Bhattacharyya et al. | Highly efficient separation of Am3+ and Eu3+ using an aqueous soluble sulfonated BTP derivative by hollow-fiber supported liquid membrane containing TODGA | |
Kumari et al. | Validation of solvent extraction scheme for the reprocessing of advanced heavy water reactor spent fuel using N, N-dihexyl octanamide as extractant | |
JP5363465B2 (ja) | プルトニウムの還元ストリッピング操作における、抗亜硝酸剤としてのブチルアルデヒドオキシムの使用 | |
Malmbeck et al. | EURO-GANEX, a Process for the Co-separation of TRU | |
Wilden et al. | Process Development and Laboratory-Scale Demonstration of a Regular-SANEX Process Using C5-BPP (2, 6-Bis (5-(2, 2-dimethylpropyl)-1 H-pyrazol-3-yl) pyridine) | |
Geist et al. | A kinetic study on the extraction of americium (III) into CyMe4-BTBP | |
Fang et al. | Recovery of Uranium in a Carbonate Solution Using Methyltrioctylammonium Carbonate as the Extractant | |
RU2574036C1 (ru) | Способ экстракционной переработки отработанного ядерного топлива аэс | |
Duan et al. | Demonstration of an improved total partitioning process for high level liquid waste using annular centrifugal contactors | |
Magnusson et al. | Partitioning of minor actinides from PUREX raffinate by the TODGA process | |
Hoshino et al. | Mechanical properties of fuel debris for defueling toward decommissioning | |
Bertrand et al. | Study of irradiated and non-irradiated MOX fuel reprocessing | |
Todd et al. | Oxidation and Extraction of Americium (VI) from Lanthanides | |
Serrano-Purroy et al. | Towards a Diamex process flowsheet using high active concentrate (HAC) | |
Serrano-Purroy et al. | First DIAMEX partitioning using genuine high active concentrate | |
Beslu et al. | PROFIP code: A model to evaluate the release of fission product from a defected fuel in PWR |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
ST | Notification of lapse |
Effective date: 20120131 |