FR2439457A1 - IMPROVEMENTS IN OR RELATING TO METHODS OF PLACING AND REMOVING BARS OF NEUTRON CONSUMABLE SUBSTANCES FROM FUEL ASSEMBLIES - Google Patents

IMPROVEMENTS IN OR RELATING TO METHODS OF PLACING AND REMOVING BARS OF NEUTRON CONSUMABLE SUBSTANCES FROM FUEL ASSEMBLIES

Info

Publication number
FR2439457A1
FR2439457A1 FR7925657A FR7925657A FR2439457A1 FR 2439457 A1 FR2439457 A1 FR 2439457A1 FR 7925657 A FR7925657 A FR 7925657A FR 7925657 A FR7925657 A FR 7925657A FR 2439457 A1 FR2439457 A1 FR 2439457A1
Authority
FR
France
Prior art keywords
placing
tail
cross
neutron
fuel assemblies
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
FR7925657A
Other languages
French (fr)
Other versions
FR2439457B1 (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.)
Babcock and Wilcox Co
Original Assignee
Babcock and Wilcox Co
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 Babcock and Wilcox Co filed Critical Babcock and Wilcox Co
Publication of FR2439457A1 publication Critical patent/FR2439457A1/en
Application granted granted Critical
Publication of FR2439457B1 publication Critical patent/FR2439457B1/fr
Granted legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/02Control of nuclear reaction by using self-regulating properties of reactor materials, e.g. Doppler effect
    • G21C7/04Control of nuclear reaction by using self-regulating properties of reactor materials, e.g. Doppler effect of burnable poisons
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/06Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
    • G21C7/10Construction of control elements
    • G21C7/117Clusters of control rods; Spider construction
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/06Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
    • G21C7/10Construction of control elements
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Catalysts (AREA)
  • Working Measures On Existing Buildindgs (AREA)
  • Clamps And Clips (AREA)
  • Mutual Connection Of Rods And Tubes (AREA)

Abstract

L'INVENTION A TRAIT A DES PERFECTIONNEMENTS APPORTES AUX ENSEMBLES DE COMBUSTIBLE DE REACTEUR NUCLEAIRE. ELLE A POUR OBJET UN PROCEDE POUR METTRE EN PLACE ET RETIRER DES BARREAUX DE "POISON" OU SUBSTANCE D'ABSORPTION DE NEUTRONS DU CROISILLON DANS UN ENSEMBLE DE COMBUSTIBLE. LE BOUCHON 56 D'UNE EXTREMITE DE CHACUN DES BARREAUX DE SUBSTANCE D'ABSORPTION DE NEUTRONS EST MUNI D'UNE QUEUE 60 QUI EST RECUE DANS UN ALESAGE RESPECTIF 64-72 PRATIQUE DANS LE CROISILLON. LA QUEUE EST DEFORMEE EN 62 POUR FIXER SOLIDEMENT LA QUEUE ET LE BARREAU DANS L'ALESAGE DU CROISILLON. UNE POUSSEE 71 EXERCEE SUR LA QUEUE DANS LE SENS AXIAL DE L'ALESAGE PERMET DE SURMONTER LA DEFORMATION POUR LIBERER LE BARREAU DU CROISILLON. APPLICATION NOTAMMENT A L'EQUIPEMENT DE REACTEURS NUCLEAIRES.THE INVENTION DETAILS OF IMPROVEMENTS TO NUCLEAR REACTOR FUEL ASSEMBLIES. ITS OBJECT A PROCESS FOR PLACING AND REMOVING "POISON" BARS OR NEUTRON ABSORBING SUBSTANCE FROM THE CROSS-BRACE IN A FUEL ASSEMBLY. THE PLUG 56 OF ONE END OF EACH OF THE NEUTRON ABSORBING SUBSTANCE BARS IS PROVIDED WITH A TAIL 60 WHICH IS RECEIVED IN A RESPECTIVE BORE 64-72 PRACTICAL IN THE CROSS-BODY. THE TAIL IS DEFORMED IN 62 TO FIX THE TAIL AND THE BAR SOLIDLY IN THE BORE OF THE CROSS-BRACE. A THRUST 71 EXERCISED ON THE TAIL IN THE AXIAL DIRECTION OF THE BALEING ALLOWS THE DEFORMATION TO BE OVERCOME TO FREE THE BAR FROM THE CROSS-BODY. APPLICATION IN PARTICULAR TO NUCLEAR REACTOR EQUIPMENT.

FR7925657A 1978-10-18 1979-10-16 IMPROVEMENTS IN OR RELATING TO METHODS OF PLACING AND REMOVING BARS OF NEUTRON CONSUMABLE SUBSTANCES FROM FUEL ASSEMBLIES Granted FR2439457A1 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US95252278A 1978-10-18 1978-10-18

Publications (2)

Publication Number Publication Date
FR2439457A1 true FR2439457A1 (en) 1980-05-16
FR2439457B1 FR2439457B1 (en) 1984-06-08

Family

ID=25492987

Family Applications (1)

Application Number Title Priority Date Filing Date
FR7925657A Granted FR2439457A1 (en) 1978-10-18 1979-10-16 IMPROVEMENTS IN OR RELATING TO METHODS OF PLACING AND REMOVING BARS OF NEUTRON CONSUMABLE SUBSTANCES FROM FUEL ASSEMBLIES

Country Status (9)

Country Link
JP (1) JPS5928875B2 (en)
CA (1) CA1132728A (en)
CH (1) CH650352A5 (en)
DE (1) DE2929465C2 (en)
ES (2) ES484631A0 (en)
FR (1) FR2439457A1 (en)
GB (2) GB2077483B (en)
IT (1) IT1124381B (en)
MX (1) MX6683E (en)

Families Citing this family (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3337636C1 (en) * 1983-10-15 1987-01-02 Brown Boveri Reaktor GmbH, 6800 Mannheim Process and device for exchanging neutron absorber rods
US4576787A (en) * 1983-12-21 1986-03-18 Westinghouse Electric Corp. Burnable absorber assembly
EP0159509B1 (en) * 1984-03-30 1989-01-04 Westinghouse Electric Corporation An improved control rod spider assembly for a nuclear reactor fuel assembly
JPS60163566U (en) * 1984-04-02 1985-10-30 ソニー株式会社 disc cassette
US4640813A (en) * 1984-09-26 1987-02-03 Westinghouse Electric Corp. Soluble burnable absorber rod for a nuclear reactor
FR2599884B1 (en) * 1986-06-10 1988-10-07 Fragema Framatome & Cogema ADJUSTMENT GRAPPLE WITH REMOVABLE PENCILS FOR NUCLEAR FUEL ASSEMBLY
FR2633435B1 (en) * 1988-06-28 1990-11-09 Framatome Sa ADJUSTABLE PENCIL ADJUSTING CLUSTER FOR NUCLEAR FUEL ASSEMBLY

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR633615A (en) * 1927-04-30 1928-02-01 Soc Fr Constr Babcock & Wilcox Process for chucking tubular parts into holes in other parts
GB1013000A (en) * 1963-12-05 1965-12-15 Combustion Eng Arrangement of a fuel assembly in combination with a control rod assembly for a nuclear reactor
FR2208730A1 (en) * 1972-12-05 1974-06-28 Kerjean Yves
FR2233587A1 (en) * 1973-06-14 1975-01-10 Chausson Usines Sa Tube bundle heat exchanger - has tube ends shaped as complementary polygons

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1152003A (en) * 1965-08-17 1969-05-14 Atomic Energy Authority Uk Improvements relating to Nuclear Reactors
GB1112946A (en) * 1965-08-10 1968-05-08 Atomic Energy Authority Uk Improvements relating to nuclear reactors

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR633615A (en) * 1927-04-30 1928-02-01 Soc Fr Constr Babcock & Wilcox Process for chucking tubular parts into holes in other parts
GB1013000A (en) * 1963-12-05 1965-12-15 Combustion Eng Arrangement of a fuel assembly in combination with a control rod assembly for a nuclear reactor
FR2208730A1 (en) * 1972-12-05 1974-06-28 Kerjean Yves
FR2233587A1 (en) * 1973-06-14 1975-01-10 Chausson Usines Sa Tube bundle heat exchanger - has tube ends shaped as complementary polygons

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
EXBK/ *

Also Published As

Publication number Publication date
GB2032163B (en) 1982-09-15
ES494899A0 (en) 1982-12-16
CA1132728A (en) 1982-09-28
MX6683E (en) 1985-10-08
IT7909548A0 (en) 1979-09-28
DE2929465A1 (en) 1980-04-24
ES8302345A1 (en) 1982-12-16
ES8101803A1 (en) 1980-12-16
ES484631A0 (en) 1980-12-16
DE2929465C2 (en) 1983-12-01
CH650352A5 (en) 1985-07-15
GB2032163A (en) 1980-04-30
JPS5557188A (en) 1980-04-26
JPS5928875B2 (en) 1984-07-16
FR2439457B1 (en) 1984-06-08
IT1124381B (en) 1986-05-07
GB2077483B (en) 1983-04-27
GB2077483A (en) 1981-12-16

Similar Documents

Publication Publication Date Title
FR2439458A1 (en) METHOD OF PLACING AND REMOVING BARS OF CONSUMABLE SUBSTANCES FOR ABSORBING NEUTRONS FROM THE CROISILLON IN A FUEL ASSEMBLY
SE8802659D0 (en) Nuclear Reactor Fuel Cartridge
ES490334A0 (en) A METHOD OF DECONTAMINATING AND WITHDRAWING CORROSION PRODUCTS, OF WHICH SOME ARE RADIOACTIVE, OF NUCLEAR REACTOR SURFACES.
SE8803006D0 (en) Nuclear Reactor Fuel Cartridge
FR2439457A1 (en) IMPROVEMENTS IN OR RELATING TO METHODS OF PLACING AND REMOVING BARS OF NEUTRON CONSUMABLE SUBSTANCES FROM FUEL ASSEMBLIES
NL7903069A (en) Apparatus for holding transverse fuel rods of an assembly for nuclear reactors.
FR2414241A1 (en) RADIONUCLEIDE GENERATOR FOR THE SEPARATION OF RADIOACTIVE SUBSTANCES
FR2354612A1 (en) FAST NUCLEAR REACTOR PROVIDED WITH A NEUTRON SHIELD IN THE FORM OF GROUPED BARS
ES8402972A1 (en) Method and tool for manufacturing a fuel assembly for a light water nuclear reactor.
BR7701641A (en) PROCESS FOR THE SEPARATION OF NOBLE, CRYPTON AND XENON GASES, WHICH CONTAIN RADIOACTIVE ISOTOPES, CUMBUST GASES, WHICH ARE PRODUCED IN THE REPRESENTATION OF NUCLEAR FUELS OR IN NUCLEAR REACTORS
GB1300502A (en) Nuclear fuel pins
FR2607823B1 (en) PROCESS FOR SEPARATING TECHNETIUM FROM AN ORGANIC SOLVENT WITH ZIRCONIUM AND AT LEAST ANOTHER METAL SUCH AS URANIUM OR PLUTONIUM, ESPECIALLY USEFUL FOR THE TREATMENT OF IRRADIATED NUCLEAR FUELS
DE3238886A1 (en) METHOD AND DEVICE FOR REMOVING DEPOSITS ON THE SURFACES OF THE COMPONENTS OF A WATER-COOLED CORE REACTOR SYSTEM
FR2377827A1 (en) METHOD AND APPARATUS FOR THE CHROMATOGRAPHIC SEPARATION OF FRUCTOSE / DEXTROSE SOLUTIONS
FR2404900A1 (en) PULSED COLUMN INTENDED FOR A SOLVENT EXTRACTION PROCESS, AND IN WHICH THE HORIZONTAL PERFORATED PLATES ARE SEPARATED BY SPACERS CONSISTING OF A NEUTRON ABSORBING METAL MATERIAL, WITH A VIEW TO THE TREATMENT OF A NUCLEAR IRBUSTIRADY FUEL
FR2410626A1 (en) PROCESS FOR OBTAINING ISOTOPES OF HYDROGEN BY PHOTODISSOCIATION OF AN ORGANIC ACID
DE2241350A1 (en) METHOD OF TESTING NEUTRON FLOW MEASURING CHANNELS ON NUCLEAR REACTORS
SE8401937D0 (en) METHOD DEVICE FOR DETERMINING THE PRESSURE IN Fission GAS RELEASED IN NUCLEAR FUEL RODS
BE895151A (en) PROCESS FOR THE DISSOLUTION OF SOLID MATERIALS, IN PARTICULAR SOLID NUCLEAR REACTOR FUELS, AND DISSOLUTION APPARATUS FOR CARRYING OUT SAID METHOD
GIBSON et al. A microprobe study of the retention of the fission gas xenon in irradiated uranium fuels dispersed in aluminum clad nuclear reactor fuel plates(Microprobe analysis of fission gas xenon retention by UAl 4 and U 3 O 8 fuels dispersed in aluminum cladding)
Donati et al. Failures of Core Shells Bolt Assemblies of the Chooz Reactor.(Retroactive Coverage)
ES8207651A1 (en) Method for acoustic and ultrasonic detection of nuclear reactor fuel assemblies having become defective in service, and corresponding detection device.
CUBICCIOTTI et al. EPRI-NASA cooperative project on stress corrosion cracking of Zircaloys(nuclear fuel failures)[Final Report]
IT8122080A1 (en) AUTOMATIC AND PROGRAMMABLE METHOD OF ASSEMBLY AND WELDING OF SPACER PLATES FOR KERNEL ELEMENTS OF FAST NUCLEAR REACTORS AND PLANT FOR ITS IMPLEMENTATION
Coffin Evaluation of Zircaloy Cladding Concepts in Cesium--Cadmium by the Localized Ductility Method

Legal Events

Date Code Title Description
ST Notification of lapse