ES8801750A1 - Procedimiento para mantener en condiciones subscritas durante su transporte y almacenamiento, los elementos combustibles utilizados en reactores nucleares de agua ligera. - Google Patents

Procedimiento para mantener en condiciones subscritas durante su transporte y almacenamiento, los elementos combustibles utilizados en reactores nucleares de agua ligera.

Info

Publication number
ES8801750A1
ES8801750A1 ES540075A ES540075A ES8801750A1 ES 8801750 A1 ES8801750 A1 ES 8801750A1 ES 540075 A ES540075 A ES 540075A ES 540075 A ES540075 A ES 540075A ES 8801750 A1 ES8801750 A1 ES 8801750A1
Authority
ES
Spain
Prior art keywords
fuel
subcriticality
sheets
keeping
fuel elements
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.)
Expired
Application number
ES540075A
Other languages
English (en)
Other versions
ES540075A0 (es
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.)
Transnuklear GmbH
Original Assignee
Transnuklear 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.)
Filing date
Publication date
Application filed by Transnuklear GmbH filed Critical Transnuklear GmbH
Publication of ES8801750A1 publication Critical patent/ES8801750A1/es
Publication of ES540075A0 publication Critical patent/ES540075A0/es
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements 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
    • G21C19/40Arrangements for preventing occurrence of critical conditions, e.g. during storage
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements 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
    • G21C19/02Details of handling arrangements
    • G21C19/06Magazines for holding fuel elements or control elements
    • G21C19/07Storage racks; Storage pools
    • 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)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

PROCEDIMIENTO PARA MANTENER EN CONDICIONES SUBCRITICAS, DURANTE SU TRANSPORTE Y ALMACENAMIENTO, LOS ELEMENTOS COMBUSTIBLES UTILIZADOS EN REACTORES NUCLEARES DE AGUA LIGERA. EL PROCESO IMPLICA LA INTRODUCCION ENTRE FILAS DE BARRAS COMBUSTIBLES (2), CHAPAS (3) CON VENENO DE NEUTRONES A PARTIR DE LOS LADOS LONGITUDINALES DE LOS ELEMENTOS COMBUSTIBLES (1). LA ANCHURA DE LAS CHAPAS RESPONDE A LA MEDIDA DE LAS ARISTAS DE LOS ELEMENTOS COMBUSTIBLES Y LA LONGITUD CORRESPONDE A LA DISTANCIA ENTRE DOS DISTANCIADORES CONTIGUOS. LAS CHAPAS CONSISTEN EN ACERO FINO CON CONTENIDO EN BORO.
ES540075A 1984-02-03 1985-02-01 Procedimiento para mantener en condiciones subscritas durante su transporte y almacenamiento, los elementos combustibles utilizados en reactores nucleares de agua ligera. Expired ES8801750A1 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE3403780A DE3403780C1 (de) 1984-02-03 1984-02-03 Verfahren zur Einhaltung der Unterkritikalitaet von Brennelementen eines Leichtwasserreaktors

Publications (2)

Publication Number Publication Date
ES8801750A1 true ES8801750A1 (es) 1988-02-16
ES540075A0 ES540075A0 (es) 1988-02-16

Family

ID=6226694

Family Applications (1)

Application Number Title Priority Date Filing Date
ES540075A Expired ES8801750A1 (es) 1984-02-03 1985-02-01 Procedimiento para mantener en condiciones subscritas durante su transporte y almacenamiento, los elementos combustibles utilizados en reactores nucleares de agua ligera.

Country Status (4)

Country Link
EP (1) EP0151306B1 (es)
JP (1) JPS60183592A (es)
DE (2) DE3403780C1 (es)
ES (1) ES8801750A1 (es)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4917856A (en) * 1988-12-08 1990-04-17 Westinghouse Electric Corp. Self-latching reactivity-reducing device for use in on-site spent fuel assembly storage
SE465901B (sv) * 1990-03-28 1991-11-11 Asea Atom Ab Saett och anordning foer att vid transport av nukleaert material, foeretraedesvis i form braenslestavar,minska risken foer kriticitet
DE19517415A1 (de) * 1995-05-16 1996-11-21 Metallveredlung Gmbh & Co Kg Verfahren zur Absorption der bei der Kernreaktion radioaktiver Materialien entstehenden Neutronen

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1460558A (fr) * 1964-05-01 1966-03-04 Reactor Centrum Nederland Système de stockage pour barres fissiles ou éléments à combustible nucléaire
US4225467A (en) * 1977-11-25 1980-09-30 The Carborundum Company Neutron absorbing article and method for manufacture of such article
DE3110582C2 (de) * 1981-03-18 1986-07-24 Kraftwerk Union AG, 4330 Mülheim Verfahren zum Manipulieren und/oder Lagern eines Kernreaktorbrennelementes

Also Published As

Publication number Publication date
EP0151306A3 (en) 1986-10-22
EP0151306B1 (de) 1989-02-08
DE3476716D1 (en) 1989-03-16
EP0151306A2 (de) 1985-08-14
DE3403780C1 (de) 1985-04-18
ES540075A0 (es) 1988-02-16
JPS60183592A (ja) 1985-09-19

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Legal Events

Date Code Title Description
FD1A Patent lapsed

Effective date: 19970303