DE602007003013D1 - Verfahren zur wiederaufbereitung von verbrauchtem kernbrennstoff und zur herstellung eines gemischten uran-plutonium-oxids - Google Patents

Verfahren zur wiederaufbereitung von verbrauchtem kernbrennstoff und zur herstellung eines gemischten uran-plutonium-oxids

Info

Publication number
DE602007003013D1
DE602007003013D1 DE200760003013 DE602007003013T DE602007003013D1 DE 602007003013 D1 DE602007003013 D1 DE 602007003013D1 DE 200760003013 DE200760003013 DE 200760003013 DE 602007003013 T DE602007003013 T DE 602007003013T DE 602007003013 D1 DE602007003013 D1 DE 602007003013D1
Authority
DE
Germany
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.)
Active
Application number
DE200760003013
Other languages
English (en)
Inventor
Pascal Baron
Binh Dinh
Michel Masson
Francois Drain
Jean-Luc Emin
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Orano Cycle SA
Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
Original Assignee
Areva NC SA
Commissariat a lEnergie Atomique CEA
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Areva NC SA, Commissariat a lEnergie Atomique CEA filed Critical Areva NC SA
Publication of DE602007003013D1 publication Critical patent/DE602007003013D1/de
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

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)
  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Geology (AREA)
  • High Energy & Nuclear Physics (AREA)
  • General Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
  • Extraction Or Liquid Replacement (AREA)
  • Oxygen, Ozone, And Oxides In General (AREA)
DE200760003013 2006-05-24 2007-05-23 Verfahren zur wiederaufbereitung von verbrauchtem kernbrennstoff und zur herstellung eines gemischten uran-plutonium-oxids Active DE602007003013D1 (de)

Applications Claiming Priority (3)

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
US85302406P 2006-10-20 2006-10-20
PCT/EP2007/055024 WO2007135178A1 (en) 2006-05-24 2007-05-23 Process for reprocessing a spent nuclear fuel and of preparing a mixed uranium-plutonium oxide

Publications (1)

Publication Number Publication Date
DE602007003013D1 true DE602007003013D1 (de) 2009-12-10

Family

ID=37892451

Family Applications (1)

Application Number Title Priority Date Filing Date
DE200760003013 Active DE602007003013D1 (de) 2006-05-24 2007-05-23 Verfahren zur wiederaufbereitung von verbrauchtem kernbrennstoff und zur herstellung eines gemischten uran-plutonium-oxids

Country Status (12)

Country Link
US (2) US20090184298A1 (de)
EP (1) EP2022061B1 (de)
JP (1) JP5325098B2 (de)
KR (1) KR101386696B1 (de)
CN (1) CN101449338B (de)
AT (1) ATE447231T1 (de)
DE (1) DE602007003013D1 (de)
ES (1) ES2334852T3 (de)
FR (1) FR2901627B1 (de)
RU (1) RU2431896C2 (de)
WO (1) WO2007135178A1 (de)
ZA (1) ZA200809415B (de)

Families Citing this family (50)

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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
US20100158772A1 (en) * 2008-06-13 2010-06-24 Decode Biostructures, Inc. Nanovolume microcapillary crystallization system
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 (en) 2010-01-13 2011-07-21 Advanced Reactor Concepts LLC Sheathed, annular metal nuclear fuel
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)
RU2684645C2 (ru) * 2014-04-14 2019-04-11 Эдвансед Реактор Консептс Ллк Керамическое ядерное топливо, диспергированное в матрице из металлического сплава
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
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
FR3039547B1 (fr) 2015-07-29 2017-08-25 Areva Nc Nouveaux n,n-dialkylamides dissymetriques, leur synthese et leurs utilisations
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
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
WO2019115394A1 (en) 2017-12-11 2019-06-20 Orano Cycle Method for preparing a powder comprising particles of triuranium octoxide and particles of plutonium dioxide
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
FR3139408A1 (fr) 2022-09-02 2024-03-08 Commissariat A L'energie Atomique Et Aux Energies Alternatives Procédé de désextraction d’uranium(vi) et d’un actinide(iv) d’une solution organique par précipitation oxalique

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Also Published As

Publication number Publication date
FR2901627A1 (fr) 2007-11-30
FR2901627B1 (fr) 2009-05-01
ZA200809415B (en) 2009-10-28
CN101449338A (zh) 2009-06-03
ES2334852T3 (es) 2010-03-16
CN101449338B (zh) 2012-10-24
US7887767B2 (en) 2011-02-15
WO2007135178A1 (en) 2007-11-29
US20070290178A1 (en) 2007-12-20
US20090184298A1 (en) 2009-07-23
RU2008151145A (ru) 2010-06-27
KR101386696B1 (ko) 2014-04-18
RU2431896C2 (ru) 2011-10-20
JP5325098B2 (ja) 2013-10-23
EP2022061B1 (de) 2009-10-28
JP2009537838A (ja) 2009-10-29
KR20090010217A (ko) 2009-01-29
ATE447231T1 (de) 2009-11-15
EP2022061A1 (de) 2009-02-11

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