NL7500663A - Treating irradiated nuclear fuel - containing plutonium and uranium oxides, in bath of sodium nitrate and peroxide - Google Patents

Treating irradiated nuclear fuel - containing plutonium and uranium oxides, in bath of sodium nitrate and peroxide

Info

Publication number
NL7500663A
NL7500663A NL7500663A NL7500663A NL7500663A NL 7500663 A NL7500663 A NL 7500663A NL 7500663 A NL7500663 A NL 7500663A NL 7500663 A NL7500663 A NL 7500663A NL 7500663 A NL7500663 A NL 7500663A
Authority
NL
Netherlands
Prior art keywords
bath
peroxide
nuclear fuel
sodium nitrate
irradiated nuclear
Prior art date
Application number
NL7500663A
Other languages
Dutch (nl)
Original Assignee
Cen Centre Energie Nucleaire
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 Cen Centre Energie Nucleaire filed Critical Cen Centre Energie Nucleaire
Publication of NL7500663A publication Critical patent/NL7500663A/en

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
    • G21C19/48—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
    • 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

Abstract

The bath is maintained at 400-500 degrees C in a dry atmos., the gaseous phase formed being removed and the solid phase being separated from the liq. phase. The bath is opt formed by dissolving Na2O in NaNO3 at 400-500 degrees C in a dry inert atmos, followed by introducing dry O2 into the uncooled bath, e.g. by bubbling. Object is to treat irradiated fuel contg. >=20 wt% Pu oxide, e.g. from rapid neutron energy consumption; and to avoid corrosion and production of nitrous gases.
NL7500663A 1974-05-17 1975-01-21 Treating irradiated nuclear fuel - containing plutonium and uranium oxides, in bath of sodium nitrate and peroxide NL7500663A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
BE144448A BE815189A (en) 1974-05-17 1974-05-17 PROCESS FOR CONDITIONING OF IRRADIATED NUCLEAR FUEL

Publications (1)

Publication Number Publication Date
NL7500663A true NL7500663A (en) 1975-11-19

Family

ID=3842663

Family Applications (1)

Application Number Title Priority Date Filing Date
NL7500663A NL7500663A (en) 1974-05-17 1975-01-21 Treating irradiated nuclear fuel - containing plutonium and uranium oxides, in bath of sodium nitrate and peroxide

Country Status (2)

Country Link
BE (1) BE815189A (en)
NL (1) NL7500663A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN103680653A (en) * 2012-09-13 2014-03-26 通用电气-日立核能美国有限责任公司 Methods of fabricating metallic fuel from surplus plutonium

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5847298A (en) * 1981-09-16 1983-03-18 日本原子力研究所 Method of pretreating in nuclear fuel reprocessing
GB9507644D0 (en) * 1995-04-12 1995-06-14 British Nuclear Fuels Plc Method of processing oxide nuclear fuel

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN103680653A (en) * 2012-09-13 2014-03-26 通用电气-日立核能美国有限责任公司 Methods of fabricating metallic fuel from surplus plutonium
US20160053391A1 (en) * 2012-09-13 2016-02-25 Ge-Hitachi Nuclear Energy Americas Llc Methods of fabricating metallic fuel from surplus plutonium
CN103680653B (en) * 2012-09-13 2018-04-10 通用电气-日立核能美国有限责任公司 By the method for unnecessary plutonium manufacture metal fuel
US10280527B2 (en) * 2012-09-13 2019-05-07 Ge-Hitachi Nuclear Energy Americas Llc Methods of fabricating metallic fuel from surplus plutonium

Also Published As

Publication number Publication date
BE815189A (en) 1974-09-16

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Legal Events

Date Code Title Description
BV The patent application has lapsed