JPH0631802B2 - 使用ずみ核燃料物質の再処理工程において回収されるウランまたはプルトニウムのバッチ式純精製法 - Google Patents

使用ずみ核燃料物質の再処理工程において回収されるウランまたはプルトニウムのバッチ式純精製法

Info

Publication number
JPH0631802B2
JPH0631802B2 JP4203985A JP4203985A JPH0631802B2 JP H0631802 B2 JPH0631802 B2 JP H0631802B2 JP 4203985 A JP4203985 A JP 4203985A JP 4203985 A JP4203985 A JP 4203985A JP H0631802 B2 JPH0631802 B2 JP H0631802B2
Authority
JP
Japan
Prior art keywords
solution
crystals
batch
mol
mother liquor
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 - Lifetime
Application number
JP4203985A
Other languages
English (en)
Japanese (ja)
Other versions
JPS60205398A (ja
Inventor
エドムント・ヘンリヒ
ウルリヒ・バウダー
ラインホルフ・ヒユフナー
ヴイリイ・レツシユ
クラウス・エーベルト
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.)
KERUNFUORUSHUNGUSUTSUENTORUMU KAARUSURUUE GmbH
Original Assignee
KERUNFUORUSHUNGUSUTSUENTORUMU KAARUSURUUE GmbH
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 KERUNFUORUSHUNGUSUTSUENTORUMU KAARUSURUUE GmbH filed Critical KERUNFUORUSHUNGUSUTSUENTORUMU KAARUSURUUE GmbH
Publication of JPS60205398A publication Critical patent/JPS60205398A/ja
Publication of JPH0631802B2 publication Critical patent/JPH0631802B2/ja
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

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
    • 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

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
JP4203985A 1984-03-05 1985-03-05 使用ずみ核燃料物質の再処理工程において回収されるウランまたはプルトニウムのバッチ式純精製法 Expired - Lifetime JPH0631802B2 (ja)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE3408029.5 1984-03-05
DE19843408029 DE3408029A1 (de) 1984-03-05 1984-03-05 Verfahren zur chargenweisen feinreinigung von in einem wiederaufarbeitungsprozess fuer bestrahlte kernbrenn- und/oder brutstoffe rueckzugewinnendem uran oder plutonium

Publications (2)

Publication Number Publication Date
JPS60205398A JPS60205398A (ja) 1985-10-16
JPH0631802B2 true JPH0631802B2 (ja) 1994-04-27

Family

ID=6229599

Family Applications (1)

Application Number Title Priority Date Filing Date
JP4203985A Expired - Lifetime JPH0631802B2 (ja) 1984-03-05 1985-03-05 使用ずみ核燃料物質の再処理工程において回収されるウランまたはプルトニウムのバッチ式純精製法

Country Status (5)

Country Link
US (1) US4759878A (enExample)
JP (1) JPH0631802B2 (enExample)
DE (1) DE3408029A1 (enExample)
FR (1) FR2560708B1 (enExample)
GB (1) GB2157276B (enExample)

Families Citing this family (15)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
HU200971B (en) * 1984-09-12 1990-09-28 Magyar Asvanyolaj Es Foeldgaz Combined separation process for reducing inactive salt content of waste solutions of atomic power stations
DE3639066A1 (de) * 1986-11-14 1988-05-19 Kernforschungsz Karlsruhe Verfahren zur verbesserung der kritikalitaetssicherheit in einem fluessig-fluessig-extraktionsprozess fuer bestrahlte kernbrenn- und/oder brutstoffe
FR2633090B1 (fr) * 1988-06-16 1992-07-31 Cogema Procede pour separer au moyen d'ethers-couronnes l'uranium et le plutonium presents dans un milieu aqueux provenant du retraitement des combustibles nucleaires irradies
US5055237A (en) * 1990-08-14 1991-10-08 Technology International Incorporated Method of compacting low-level radioactive waste utilizing freezing and electrodialyzing concentration processes
JP2551683B2 (ja) * 1990-10-01 1996-11-06 動力炉・核燃料開発事業団 ウラン・プルトニウム混合溶液からのウランおよびプルトニウムの分離方法
JP2529457B2 (ja) * 1990-10-01 1996-08-28 動力炉・核燃料開発事業団 硝酸プルトニウム溶液の低温濃縮方法
US5640668A (en) * 1996-03-20 1997-06-17 Krot; Nikolai N. Removal of dissolved actinides from alkaline solutions by the method of appearing reagents
JP2948166B2 (ja) * 1997-04-04 1999-09-13 核燃料サイクル開発機構 使用済核燃料からの超ウラン元素の回収方法
AU7605498A (en) * 1997-05-28 1998-12-30 James A. Patterson System for producing heat and deactivating a radioactive substance by electrolysis
JP2003215287A (ja) * 2002-01-17 2003-07-30 Japan Nuclear Cycle Development Inst States Of Projects 共晶析現象を利用した使用済核燃料の再処理方法
RU2244966C2 (ru) * 2003-03-20 2005-01-20 Российская Федерация в лице Министерства Российской Федерации по атомной энергии Способ очистки нитрата уранила от продуктов деления и устройство для его осуществления
RU2268510C2 (ru) * 2004-02-24 2006-01-20 Российская Федерация в лице Министерства РФ по атомной энергии Способ очистки нитрата уранила от продуктов деления и устройство для его осуществления
US8845993B2 (en) * 2010-01-20 2014-09-30 Eestor, Inc. Purification of barium ion source
RU2427938C1 (ru) * 2010-01-26 2011-08-27 Открытое акционерное общество "Сибирский химический комбинат" Устройство для очистки нитрата уранила от продуктов деления
US8597471B2 (en) 2010-08-19 2013-12-03 Industrial Idea Partners, Inc. Heat driven concentrator with alternate condensers

Family Cites Families (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2811415A (en) * 1943-04-03 1957-10-29 Glenn T Seaborg Extraction method for separating uranium, plutonium, and fission products from compositions containing same
US2871251A (en) * 1944-11-30 1959-01-27 John W Gofman Process for the separation of heavy metals
US4182652A (en) * 1974-12-17 1980-01-08 Puechl Karl H Nuclear fuel element, core for nuclear reactor, nuclear fuel material
US4278559A (en) * 1978-02-16 1981-07-14 Electric Power Research Institute Method for processing spent nuclear reactor fuel
DE2811959C3 (de) * 1978-03-18 1980-09-25 Alkem Gmbh, 6450 Hanau Verfahren zur Herstellung von (U/Pu)02 -Mischkristallen
DE3245051C2 (de) * 1982-12-06 1986-09-25 Alkem Gmbh, 6450 Hanau Verfahren zum Herstellen von PuO↓2↓-haltigen Kristallen
DE3336788A1 (de) * 1983-10-10 1985-04-25 Alkem Gmbh, 6450 Hanau Verfahren zum gewinnen von gereinigtem uranylnitrat

Also Published As

Publication number Publication date
GB8505585D0 (en) 1985-05-22
DE3408029C2 (enExample) 1991-06-20
JPS60205398A (ja) 1985-10-16
DE3408029A1 (de) 1985-09-12
GB2157276B (en) 1987-10-07
GB2157276A (en) 1985-10-23
US4759878A (en) 1988-07-26
FR2560708A1 (fr) 1985-09-06
FR2560708B1 (fr) 1989-12-22

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