EP0245588A2 - Procédé de purification poussée du molybdène de fission - Google Patents

Procédé de purification poussée du molybdène de fission Download PDF

Info

Publication number: EP0245588A2
Authority: EP; European Patent Office
Prior art keywords: molybdenum; sorption; space; oxide; carrier gas
Prior art date: 1986-05-15
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.): Granted

Application number

EP87102017A

Other languages

German (de)

English (en)

Other versions

EP0245588A3 (en

EP0245588B1 (fr

Inventor

Jochen Bürck

Sameh Dr. Abdel Hadi Ali

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.)

Karlsruher Institut fuer Technologie KIT

Original Assignee

Kernforschungszentrum Karlsruhe 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.)

1986-05-15

Filing date

1987-02-13

Publication date

1987-11-19

1987-02-13 Application filed by Kernforschungszentrum Karlsruhe GmbH filed Critical Kernforschungszentrum Karlsruhe GmbH

1987-11-19 Publication of EP0245588A2 publication Critical patent/EP0245588A2/fr

1988-07-06 Publication of EP0245588A3 publication Critical patent/EP0245588A3/de

1990-06-27 Application granted granted Critical

1990-06-27 Publication of EP0245588B1 publication Critical patent/EP0245588B1/fr

2007-02-13 Anticipated expiration legal-status Critical

Status Expired - Lifetime legal-status Critical Current

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Classifications

- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
- G21G4/00—Radioactive sources
- G21G4/04—Radioactive sources other than neutron sources
- G21G4/06—Radioactive sources other than neutron sources characterised by constructional features
- G21G4/08—Radioactive sources other than neutron sources characterised by constructional features specially adapted for medical application

Definitions

the radioactive, relatively short-lived nuclide technetium-99m is used in nuclear medicine. For this purpose, it is separated from the mother nuclide / daughter nuclide equilibrium as a daughter of molybdenum-99 as shortly as possible before use.
the production of the mother nuclide Mo-99 is known.
a uranium-aluminum alloy with the approximate composition UA1 3 which is mostly referred to as UA1 due to the often different aluminum content, is used after five to ten days of neutron irradiation in a nuclear reactor with forced cooling and after a subsequent cooling period of approximately one day UAl 3 targets the Mo-99 after a series of chemical process steps.
the target plates are dissolved, for example, in three to six molar sodium hydroxide solution, with a solid residue and exhaust gas being formed in addition to the alkaline solution.
the exhaust gas includes Xe-133, Xe-135, Kr-85 and J-131.
U0 2 and Na 2 U 2 O 7 are found in the solid residue.
the solution contains aluminum ions and fission products, such as. B. ions of alkali and alkaline earth metals, as well as iodine, tin and molybdenum and smaller amounts of ions of poorly soluble elements such as cerium, ruthenium and zirconium.
the desorption step of the method according to the invention is carried out in a device as described in the characterizing part of claims 7 to 10.
a carrier amount of inactive molybdate in the form of (MH 4 ) 6 Mo 7 O 24 is added to each sublimation flask for more complete sublimation of the Mo-99, which should not exceed 40 mg Mo per sublimation flask.
a direct sublimation of the Mo-99 activity from the Al203 is not possible.
the inventive method is based on j exemplary sorption and desorption experiments with various amphoteric metal oxides and with aqueous, Mo-99-indicator-containing simulant solutions of non-radioactive carrier ions of the species, the acidified in real eluate of the last organic ion exchanger are present described in more detail 5 and the results in connection with the figures illustrated. It should be noted that the application of the method to real eluates in radioactive operation can be expected to improve the fine cleaning of the Mo-99 or to increase the decontamination factors with regard to the contaminating crevice nuclides compared to the decontamination factors that the experiments listed here performed.
the concentrations of the elements investigated in the sorption and desorption experiments corresponded to those molarities (10- 5 - 10 -3 mol / l) of fission products occurring in the known fission molybdenum 99 separation process, if due to process disturbances in the previous chromatographic separation steps (pre-cleaning) complete breakthrough in activity would take place until the final fine cleaning measures of the method according to the invention.
additional Mo decontamination by means of the described method, the most unfavorable conditions were chosen in relation to the presence of other fission products.
an insert made of, for example, a Pt crucible with a drilled or perforated bottom, which receives the loaded metal oxide, can seal off the space 2 from the gas feed 4 during the sublimation of the Mo-99-0xide.
the heater 8 of the device is not limited to an inductive heater, but can be formed by other usable heating devices acting on the room 2 from the outside.

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Chemical & Material Sciences (AREA)
Chemical Kinetics & Catalysis (AREA)
General Chemical & Material Sciences (AREA)
Physics & Mathematics (AREA)
Engineering & Computer Science (AREA)
General Engineering & Computer Science (AREA)
High Energy & Nuclear Physics (AREA)
Solid-Sorbent Or Filter-Aiding Compositions (AREA)
Inorganic Compounds Of Heavy Metals (AREA)

EP87102017A 1986-05-15 1987-02-13 Procédé de purification poussée du molybdène de fission Expired - Lifetime EP0245588B1 (fr)

Applications Claiming Priority (2)

Application Number	Priority Date	Filing Date	Title
DE3616391		1986-05-15
DE19863616391 DE3616391A1 (de)	1986-05-15	1986-05-15	Verfahren zur feinreinigung von spaltmolybdaen

Publications (3)

Publication Number	Publication Date
EP0245588A2 true EP0245588A2 (fr)	1987-11-19
EP0245588A3 EP0245588A3 (en)	1988-07-06
EP0245588B1 EP0245588B1 (fr)	1990-06-27

Family

ID=6300903

Family Applications (1)

Application Number	Title	Priority Date	Filing Date
EP87102017A Expired - Lifetime EP0245588B1 (fr)	1986-05-15	1987-02-13	Procédé de purification poussée du molybdène de fission

Country Status (3)

Country	Link
US (1)	US4981658A (fr)
EP (1)	EP0245588B1 (fr)
DE (2)	DE3616391A1 (fr)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number	Priority date	Publication date	Assignee	Title
GB2227599A (en) *	1989-01-28	1990-08-01	Doryokuro Kakunenryo	Method of treatment of high-level radioactive waste
WO1994007247A1 (fr) *	1992-09-24	1994-03-31	Kernforschungszentrum Karlsruhe Gmbh	Procede pour la separation de molybdene de fission
CN110129573A (zh) *	2019-06-25	2019-08-16	国家能源投资集团有限责任公司	含钼催化剂中钼金属的回收装置及回收方法

Families Citing this family (9)

* Cited by examiner, † Cited by third party
Publication number	Priority date	Publication date	Assignee	Title
US5802439A (en) *	1997-02-19	1998-09-01	Lockheed Martin Idaho Technologies Company	Method for the production of 99m Tc compositions from 99 Mo-containing materials
US5802438A (en) *	1997-02-19	1998-09-01	Lockheed Martin Idaho Technologies Company	Method for generating a crystalline 99 MoO3 product and the isolation 99m Tc compositions therefrom
US6337055B1 (en) *	2000-01-21	2002-01-08	Tci Incorporated	Inorganic sorbent for molybdenum-99 extraction from irradiated uranium solutions and its method of use
WO2011103334A1 (fr) *	2010-02-19	2011-08-25	Babcock & Wilcox	Procédé et appareil pour l'extraction et le traitement de molybdène-99
US8450629B2 (en) *	2010-05-10	2013-05-28	Los Alamos National Security, Llc	Method of producing molybdenum-99
RU2525127C1 (ru) *	2012-12-27	2014-08-10	Федеральное государственное бюджетное образовательное учреждение высшего профессионального образования "Московский государственный машиностроительный университет (МАМИ)"	Способ сорбционного извлечения молибдена
BE1023851B1 (fr) *	2016-06-28	2017-08-14	Institut National Des Radioéléments	Procédé de production d'une fraction de radio-isotopes d'iode, en particulier d'i-131, fraction de radio-isotopes d'iode, en particulier d'i-131
JP7773185B2 (ja) *	2021-11-09	2025-11-19	株式会社千代田テクノル	テクネチウムの昇華型熱分離方法及び装置
CN116377255A (zh) *	2023-04-06	2023-07-04	中国科学院近代物理研究所	一种从α粒子辐照的锆靶中分离钼-99的方法

Family Cites Families (7)

* Cited by examiner, † Cited by third party
Publication number	Priority date	Publication date	Assignee	Title
US3799883A (en) *	1971-06-30	1974-03-26	Union Carbide Corp	Production of high purity fission product molybdenum-99
US3830746A (en) *	1972-07-27	1974-08-20	Mallinckrodt Chemical Works	Method for preparing technetium-99m generators loaded with fission product molybdenum-99
NL165872C (nl) *	1973-02-20	1981-05-15	Byk Mallinckrodt Cil Bv	Isotopengenerator voor de produktie van 99m tc bevattende vloeistoffen.
JPS5233280B2 (fr) *	1974-02-07	1977-08-26
DE2610948C3 (de) *	1976-03-16	1980-01-10	Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe	Verfahren zur Gewinnung von Molybdän -99 aus mit Neutronen bestrahlter, spaltbare Stoffe und Spaltprodukte enthaltender Matrix
US4123498A (en) *	1977-02-17	1978-10-31	General Electric Company	Process for separating fission product molybdenum from an irradiated target material
DD136385B1 (de) *	1978-05-05	1982-05-26	Akad Wissenschaften Ddr	Verfahren zur gewinnung von hoch 99 mo

1986
- 1986-05-15 DE DE19863616391 patent/DE3616391A1/de not_active Withdrawn
1987
- 1987-02-13 EP EP87102017A patent/EP0245588B1/fr not_active Expired - Lifetime
- 1987-02-13 DE DE8787102017T patent/DE3763468D1/de not_active Expired - Lifetime
1989
- 1989-05-09 US US07/349,185 patent/US4981658A/en not_active Expired - Lifetime

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number	Priority date	Publication date	Assignee	Title
GB2227599A (en) *	1989-01-28	1990-08-01	Doryokuro Kakunenryo	Method of treatment of high-level radioactive waste
AU628468B2 (en) *	1989-01-28	1992-09-17	Japan Nuclear Cycle Development Institute	Method of treatment of high-level radioactive waste
GB2227599B (en) *	1989-01-28	1992-12-23	Doryokuro Kakunenryo	Method of treatment of high-level radioactive waste
WO1994007247A1 (fr) *	1992-09-24	1994-03-31	Kernforschungszentrum Karlsruhe Gmbh	Procede pour la separation de molybdene de fission
US5508010A (en) *	1992-09-24	1996-04-16	Forschungszenlrum Karlsruhe Gmbh	Method of separating fission molybdenum
CN110129573A (zh) *	2019-06-25	2019-08-16	国家能源投资集团有限责任公司	含钼催化剂中钼金属的回收装置及回收方法

Also Published As

Publication number	Publication date
EP0245588A3 (en)	1988-07-06
DE3763468D1 (de)	1990-08-02
EP0245588B1 (fr)	1990-06-27
US4981658A (en)	1991-01-01
DE3616391A1 (de)	1987-11-19

Legal Events

Date	Code	Title	Description
1987-10-03	PUAI	Public reference made under article 153(3) epc to a published international application that has entered the european phase	Free format text: ORIGINAL CODE: 0009012
1987-11-19	AK	Designated contracting states	Kind code of ref document: A2 Designated state(s): BE DE FR GB
1988-05-19	PUAL	Search report despatched	Free format text: ORIGINAL CODE: 0009013
1988-07-06	AK	Designated contracting states	Kind code of ref document: A3 Designated state(s): BE DE FR GB
1988-08-17	17P	Request for examination filed	Effective date: 19880618
1989-11-08	17Q	First examination report despatched	Effective date: 19890926
1990-05-12	GRAA	(expected) grant	Free format text: ORIGINAL CODE: 0009210
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1990-08-02	REF	Corresponds to:	Ref document number: 3763468 Country of ref document: DE Date of ref document: 19900802
1990-08-17	ET	Fr: translation filed
1990-10-31	GBT	Gb: translation of ep patent filed (gb section 77(6)(a)/1977)
1991-04-27	PLBE	No opposition filed within time limit	Free format text: ORIGINAL CODE: 0009261
1991-04-27	STAA	Information on the status of an ep patent application or granted ep patent	Free format text: STATUS: NO OPPOSITION FILED WITHIN TIME LIMIT
1991-06-19	26N	No opposition filed
2002-01-01	REG	Reference to a national code	Ref country code: GB Ref legal event code: IF02
2003-12-23	PGFP	Annual fee paid to national office [announced via postgrant information from national office to epo]	Ref country code: GB Payment date: 20031223 Year of fee payment: 18
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2005-08-31	BERE	Be: lapsed	Owner name: KERNFORSCHUNGSZENTRUM KARLSRUHE G.M.B.H. Effective date*: 20050228
2005-10-05	GBPC	Gb: european patent ceased through non-payment of renewal fee	Effective date: 20050212
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Publication	Publication Date	Title
DE2610948C3 (de)	1980-01-10	Verfahren zur Gewinnung von Molybdän -99 aus mit Neutronen bestrahlter, spaltbare Stoffe und Spaltprodukte enthaltender Matrix
DE60209818T2 (de)	2006-11-09	Verfahren und vorrichtung zur trennung der ionen von metallischen elementen in wässriger lösung
US4738834A (en)	1988-04-19	Treatment of technetium containing solutions
DE2231976B2 (de)	1979-07-19	Verfahren zur Herstellung von hochreinem, radioaktivem Molybdän-99-Spaltprodukt
EP0245588B1 (fr)	1990-06-27	Procédé de purification poussée du molybdène de fission
DE1215669B (de)	1966-05-05	Verfahren zum Aufbereiten von bestrahltem Kernreaktorbrennstoff
DE2806502A1 (de)	1978-08-24	Verfahren zum abtrennen des spaltproduktes molybdaen aus einem bestrahlten targetmaterial
DE4231997C1 (de)	1994-01-05	Verfahren zum Abtrennen von Spaltmolybdän
CH719832B1 (de)	2025-09-15	Generatoren auf der basis von titandioxid für die erzeugung von ac-225
DE69216795T2 (de)	1997-05-07	Verfahren zur Dekontaminierung von Übergangsmetall
DE1758118C3 (de)	1974-05-30	Verfahren zur Gewinnung von radioaktivem Technetium-99m
DE3144974C2 (de)	1986-01-09	Verfahren zur Abtrennung von Aktinoidenionen aus wäßrigen, basischen, carbonathaltigen Lösungen
DE69105884T2 (de)	1995-05-04	Verfahren zum Entfernen von Cesium aus wässrigen Lösungen mit hoher Salpetersäurekonzentration.
DE69228095T2 (de)	1999-09-02	Verfahren zur Regenerierung eines Tannin-Adsorbent
DE2140998B2 (fr)	1974-07-25
DE2845613A1 (de)	1979-04-26	Verfahren und vorrichtung zum erzeugen von technetium-99m
DE2207309B2 (de)	1980-11-20	Isotopengenerator
DE2603595A1 (de)	1976-08-26	Verfahren zur erhoehung der radioaktiven konzentration von technetium- 99m und vorrichtung zur durchfuehrung des verfahrens
EP0170796B1 (fr)	1993-04-14	Procédé pour séparer de grandes quantités d'uranium à partir de faibles quantités de produits de fission radio-actifs présents dans des solutions aqueuses basiques contenant du carbonate
DE102008064682B4 (de)	2012-02-16	Anionisches Boranpolymer, sowie dessen Verwendung und Herstellung
US2877093A (en)	1959-03-10	Adsorption method for separating metal cations
DE2610947A1 (de)	1977-09-22	Verfahren zur gewinnung von molybdaen-99 aus mit neutronen bestrahlter, spaltbare stoffe und spaltprodukte enthaltender matrix
DE2627540A1 (de)	1978-01-05	Verfahren zur selektiven trennung von uran aus loesungen mittels eines ionenaustauschers
EP0347625B1 (fr)	1993-10-20	Procédé pour la séparation de technétium, de ruthénium et de palladium par des solutions de combustible nucléaire
EP3750172B1 (fr)	2023-03-22	Procédé de séparation de cesium et de téchnetium