FR2085603A1 - Processing of nuclear fuel rods - Google Patents

Processing of nuclear fuel rods

Info

Publication number
FR2085603A1
FR2085603A1 FR7107424A FR7107424A FR2085603A1 FR 2085603 A1 FR2085603 A1 FR 2085603A1 FR 7107424 A FR7107424 A FR 7107424A FR 7107424 A FR7107424 A FR 7107424A FR 2085603 A1 FR2085603 A1 FR 2085603A1
Authority
FR
France
Prior art keywords
processing
elements
nuclear fuel
fuel rods
nuclear
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.)
Granted
Application number
FR7107424A
Other languages
French (fr)
Other versions
FR2085603B1 (en
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.)
STUDIECENTRUM KERNENERGI
Original Assignee
STUDIECENTRUM KERNENERGI
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 STUDIECENTRUM KERNENERGI filed Critical STUDIECENTRUM KERNENERGI
Publication of FR2085603A1 publication Critical patent/FR2085603A1/en
Application granted granted Critical
Publication of FR2085603B1 publication Critical patent/FR2085603B1/fr
Granted 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
    • G21C19/34—Apparatus or processes for dismantling nuclear fuel, e.g. before reprocessing ; Apparatus or processes for dismantling strings of spent fuel elements
    • G21C19/38—Chemical means only
    • 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

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • General Chemical & Material Sciences (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Physical Or Chemical Processes And Apparatus (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The casings are removed from nuclear fission elements from nuclear reactors with fast neutrons by bringing the elements into contact with a liquid reagent containing water and hydrogen fluoride, which is circulated along the elements at a rate sufficient to conduct away the produced heat.
FR7107424A 1970-03-04 1971-03-04 Processing of nuclear fuel rods Granted FR2085603A1 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
BE746819 1970-03-04

Publications (2)

Publication Number Publication Date
FR2085603A1 true FR2085603A1 (en) 1971-12-24
FR2085603B1 FR2085603B1 (en) 1974-05-31

Family

ID=3856157

Family Applications (1)

Application Number Title Priority Date Filing Date
FR7107424A Granted FR2085603A1 (en) 1970-03-04 1971-03-04 Processing of nuclear fuel rods

Country Status (4)

Country Link
BE (1) BE746819A (en)
DE (1) DE2110419C3 (en)
FR (1) FR2085603A1 (en)
NL (1) NL143716B (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2390808A1 (en) * 1977-05-11 1978-12-08 Atomic Energy Authority Uk PROCESS FOR RECOVERING COMBUSTIBLE MATERIALS FROM IRRADIATED NUCLEAR FUEL ASSEMBLIES
EP0396002A2 (en) * 1989-04-28 1990-11-07 Dainippon Screen Mfg. Co., Ltd. Surface treating apparatus and method using vapor

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4174369A (en) * 1976-12-13 1979-11-13 Westinghouse Electric Corp. Fluid pressure method for recovering fuel pellets from nuclear fuel elements
JPH02103496A (en) * 1988-10-12 1990-04-16 Power Reactor & Nuclear Fuel Dev Corp Dissolution method of spent nuclear fuel and the like utilizing supersonic wave

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
NEANT *

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2390808A1 (en) * 1977-05-11 1978-12-08 Atomic Energy Authority Uk PROCESS FOR RECOVERING COMBUSTIBLE MATERIALS FROM IRRADIATED NUCLEAR FUEL ASSEMBLIES
EP0396002A2 (en) * 1989-04-28 1990-11-07 Dainippon Screen Mfg. Co., Ltd. Surface treating apparatus and method using vapor
EP0396002A3 (en) * 1989-04-28 1991-01-02 Dainippon Screen Mfg. Co., Ltd. Surface treating apparatus and method using vapor
US5174855A (en) * 1989-04-28 1992-12-29 Dainippon Screen Mfg. Co. Ltd. Surface treating apparatus and method using vapor

Also Published As

Publication number Publication date
NL143716B (en) 1974-10-15
DE2110419C3 (en) 1975-12-18
DE2110419B2 (en) 1975-04-30
DE2110419A1 (en) 1971-09-23
FR2085603B1 (en) 1974-05-31
NL7004817A (en) 1971-09-07
BE746819A (en) 1970-08-17

Similar Documents

Publication Publication Date Title
IT971105B (en) ASSEMBLY FOR IN OPERATION IN OPERATION OF A NUCLEAR REACTOR VESSEL
GB852293A (en) Improvements in boiling reactors
GB1463148A (en) Liquid cooled nuclear reactors
CH376587A (en) Solid nuclear reactor moderator
GB1189015A (en) Process and Apparatus for Removing Protium and Tritium from Heavy Water
DK136558B (en) Method for increasing the circulation of the coolant in a pressure vessel of an atomic core reactor with natural circulation of the coolant in the pressure vessel using a jet pump.
IT1052754B (en) SET OF FUEL RODS FOR NUCLEAR REACTORS..WITH EASY MOUNTING COMPONENTS
IT944491B (en) PROCEDURE FOR PRODUCING AMMONIUM DIURANATE PARTICULARLY FOR IMPLEMENT IN NUCLEAR REACTORS
SE7409299L (en)
FR1480126A (en) Large-scale fast neutron breeder nuclear reactor
FR2085603A1 (en) Processing of nuclear fuel rods
GB919637A (en) Nuclear power reactor
DK139770B (en) Fuel unit for a nuclear reactor with parallel fuel rods.
ES430594A1 (en) Purification installation for the liquid metal cooling the core of a fst-neutron nuclear rector
CH356545A (en) Nuclear reactor moderator
GB1108512A (en) Improvements relating to gas-cooled nuclear reactors
IT965106B (en) NUCLEAR FUEL GROUP PARTICULARLY FOR FAST NEUTRON REACTOR
GB933523A (en) Nuclear reactor
FR2060202A1 (en) Simulation of nuclear reactor core conduit-ions
AT310311B (en) Liquid-cooled nuclear reactor with a cylindrical pressure vessel
CH439506A (en) Water-cooled nuclear reactor with supercritical moderator pressure
CH369217A (en) Moderator boiler for heterogeneous nuclear reactors with reactor vessel
FR2037141A1 (en) Fuel system for nuclear reactors rotation
AU293578B2 (en) Nuclear reactor vessel with pressure tubes forthe liquid moderator
GB1412999A (en) Neutron screening apparatus

Legal Events

Date Code Title Description
ST Notification of lapse