GB1306896A - Creación de Inventos y Patentes con Inteligencia Artificial

GB1306896A – Removal of plutonium from plutonium hexafluorideuranium hexafluoride mixtures
– Google Patents

GB1306896A – Removal of plutonium from plutonium hexafluorideuranium hexafluoride mixtures
– Google Patents
Removal of plutonium from plutonium hexafluorideuranium hexafluoride mixtures

Info

Publication number
GB1306896A

GB1306896A
GB4378571A
GB4378571A
GB1306896A
GB 1306896 A
GB1306896 A
GB 1306896A
GB 4378571 A
GB4378571 A
GB 4378571A
GB 4378571 A
GB4378571 A
GB 4378571A
GB 1306896 A
GB1306896 A
GB 1306896A
Authority
GB
United Kingdom
Prior art keywords
plutonium
puf
fluoride
separation
deposited
Prior art date
1970-10-20
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

Application number
GB4378571A
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.)

US Atomic Energy Commission (AEC)

Original Assignee
US Atomic Energy Commission (AEC)
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.)
1970-10-20
Filing date
1971-09-20
Publication date
1973-02-14

1971-09-20
Application filed by US Atomic Energy Commission (AEC)
filed
Critical
US Atomic Energy Commission (AEC)

1973-02-14
Publication of GB1306896A
publication
Critical
patent/GB1306896A/en

Status
Expired
legal-status
Critical
Current

Links

Espacenet

Global Dossier

Discuss

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

G21C19/48—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

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

Abstract

1306896 Plutonium separation UNITED STATES ATOMIC ENERGY COMMISSION 20 Sept 1971 [20 Oct 1970] 43785/71 Heading G6R [Also in Division C1] Plutonium is separated from a UF 6 -PuF 6 mixture by contacting the mixture with particulate cobaltous fluoride at a temperature (e.g. 134-1000‹ F.) such that PuF 6 is selectively reduced to a lower fluoride which is deposited on the cobaltous fluoride. Porous cobaltous fluoride pellets may be prepared by a procedure described in USA Specification 3,372,004. The separation process may constitute the final step in the treatment of spent nuclear fuel in order to produce UF 6 having a Pu content less than 1 part per 109 suitable for isotope separation by gaseous diffusion. Deposited PuF 4 may be reconverted to PuF 6 by passage of F 2 gas at 700-900‹ F. and the porous bed may be regenerated by treatment with H 2 at 400-500‹ F.

GB4378571A
1970-10-20
1971-09-20
Removal of plutonium from plutonium hexafluorideuranium hexafluoride mixtures

Expired

GB1306896A
(en)

Applications Claiming Priority (1)

Application Number
Priority Date
Filing Date
Title

US8250870A

1970-10-20
1970-10-20

Publications (1)

Publication Number
Publication Date

GB1306896A
true

GB1306896A
(en)

1973-02-14

Family
ID=22171651
Family Applications (1)

Application Number
Title
Priority Date
Filing Date

GB4378571A
Expired

GB1306896A
(en)

1970-10-20
1971-09-20
Removal of plutonium from plutonium hexafluorideuranium hexafluoride mixtures

Country Status (6)

Country
Link

US
(1)

US3708568A
(en)

BE
(1)

BE774058A
(en)

DE
(1)

DE2151722A1
(en)

FR
(1)

FR2111730B1
(en)

GB
(1)

GB1306896A
(en)

IT
(1)

IT946176B
(en)

Families Citing this family (10)

* Cited by examiner, † Cited by third party

Publication number
Priority date
Publication date
Assignee
Title

US4096231A
(en)

1976-11-18
1978-06-20
Exxon Research And Engineering Company
Separation of uranium hexafluoride from plutonium hexafluoride by means of selective intercalation in graphite

US4364906A
(en)

1980-11-24
1982-12-21
The United States Of America As Represented By The United States Department Of Energy
Method for selectively removing fluorine and fluorine-containing contaminants from gaseous UF6

FR2521974A1
(en)

1982-02-24
1983-08-26
Commissariat Energie Atomique

PROCESS FOR PREPARING POROUS PRODUCTS BASED ON COBALT FLUORIDE OR LEAD FLUORIDE AND USE FOR THE PURIFICATION OF URANIUM HEXAFLUORIDE OF COBALT FLUORIDE-BASED BALLS OR COMPOSITE ELEMENTS

FR2521973A1
(en)

1982-02-24
1983-08-26
Commissariat Energie Atomique

PROCESS FOR PURIFYING URANIUM HEXAFLUORIDE CONTAINING TRACES OF PLUTONIUM FLUORIDE AND / OR NEPTUNIUM FLUORIDE

US4522794A
(en)

1983-08-25
1985-06-11
The United States Of America As Represented By The Department Of Energy
Fluorination process using catalyst

US4555318A
(en)

1984-01-06
1985-11-26
The United States Of America As Represented By The United States Department Of Energy
Removal of fluoride impurities from UF6 gas

FR2687140B1
(en)

1992-02-11
1994-05-13
Pechiney Uranium

METHOD FOR RECOVERING AND PURIFYING A HIGHLY ENRICHED URANIUM-BASED METAL ALLOY.

JP4196173B2
(en)

2003-01-28
2008-12-17
日立Ｇｅニュークリア・エナジー株式会社

Method for reprocessing spent nuclear fuel

JP4029193B2
(en)

2004-07-30
2008-01-09
独立行政法人日本原子力研究開発機構

Reprocessing method by fluoride volatilization method using solid-gas separation method

JP4022608B2
(en)

2004-07-30
2007-12-19
独立行政法人日本原子力研究開発機構

Reprocessing method by fluoride volatilization method using fractional distillation

Family Cites Families (5)

* Cited by examiner, † Cited by third party

Publication number
Priority date
Publication date
Assignee
Title

US2843453A
(en)

1947-04-18
1958-07-15
Robert E Connick
Separation of plutonyl ions

DE1250801B
(en)

1962-04-02
1967-09-28
United States Atomic Energy Commission, Washington, D.C. (V. St. A.)

Process for the separation of volatile fluoride impurities from uranium hexafluoride

US3178258A
(en)

1962-08-30
1965-04-13
George I Cathers
Separation of plutonium hexafluoride from uranium hexafluoride by selective sorption

US3423190A
(en)

1967-12-14
1969-01-21
Atomic Energy Commission
Plutonium tetrafluoride preparation and separation by sorption on sodium fluoride

US3615267A
(en)

1969-03-11
1971-10-26
Atomic Energy Commission
Separation of neptunium from uranium hexafluoride containing the same

1970

1970-10-20
US
US3708568D
patent/US3708568A/en
not_active
Expired – Lifetime

1971

1971-09-20
GB
GB4378571A
patent/GB1306896A/en
not_active
Expired

1971-10-18
BE
BE774058A
patent/BE774058A/en
not_active
IP Right Cessation

1971-10-18
DE
DE19712151722
patent/DE2151722A1/en
active
Pending

1971-10-19
IT
IT4166671A
patent/IT946176B/en
active

1971-10-20
FR
FR7137718A
patent/FR2111730B1/fr
not_active
Expired

Also Published As

Publication number
Publication date

IT946176B
(en)

1973-05-21

AU3420871A
(en)

1973-04-12

FR2111730B1
(en)

1976-08-20

BE774058A
(en)

1972-02-14

FR2111730A1
(en)

1972-06-09

US3708568A
(en)

1973-01-02

DE2151722A1
(en)

1972-04-27

Información de contacto