FR2317127A1 - Transport module for elongated articles partic. nuclear fuel rods - holds these clamped during transport but releases them at the reception point automatically - Google Patents

Transport module for elongated articles partic. nuclear fuel rods - holds these clamped during transport but releases them at the reception point automatically

Info

Publication number
FR2317127A1
FR2317127A1 FR7521284A FR7521284A FR2317127A1 FR 2317127 A1 FR2317127 A1 FR 2317127A1 FR 7521284 A FR7521284 A FR 7521284A FR 7521284 A FR7521284 A FR 7521284A FR 2317127 A1 FR2317127 A1 FR 2317127A1
Authority
FR
France
Prior art keywords
reception point
fuel rods
partic
releases
holds
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
FR7521284A
Other languages
French (fr)
Other versions
FR2317127B1 (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.)
Gallay SA
Original Assignee
Gallay SA
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 Gallay SA filed Critical Gallay SA
Priority to FR7521284A priority Critical patent/FR2317127A1/en
Publication of FR2317127A1 publication Critical patent/FR2317127A1/en
Application granted granted Critical
Publication of FR2317127B1 publication Critical patent/FR2317127B1/fr
Granted 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
    • G21C19/02Details of handling arrangements
    • G21C19/06Magazines for holding fuel elements or control elements
    • BPERFORMING OPERATIONS; TRANSPORTING
    • B60VEHICLES IN GENERAL
    • B60PVEHICLES ADAPTED FOR LOAD TRANSPORTATION OR TO TRANSPORT, TO CARRY, OR TO COMPRISE SPECIAL LOADS OR OBJECTS
    • B60P3/00Vehicles adapted to transport, to carry or to comprise special loads or objects
    • 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
    • G21C19/18Apparatus for bringing fuel elements to the reactor charge area, e.g. from a storage place
    • 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

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Health & Medical Sciences (AREA)
  • Public Health (AREA)
  • Transportation (AREA)
  • Mechanical Engineering (AREA)
  • De-Stacking Of Articles (AREA)

Abstract

The module comprises a series of superimposed horizontal supports fixed to vertical columns, each support having a large number of parallel storage positions each designed to receive one of the articles to be transported. The module is provided with a series of flexible retaining elements, each designed to press against an article with one of its ends and connected to a vertical fixed support. The retaining elements are free to pivot in a vertical plane and are fixed to a vertical metal sheet which can be displaced against the action of return devices, from a position corresponding to the low position of elements to a high position of these, whereby the articles are then liberated. Displacement from the metal sheet can only be obtained by cooperation of means connected to the sheet and suitable devices provided at the article reception point. Enables the fuel rods to be securely held during transfer from storage to a reception point, without human intervention and for the rods to be released at the reception point for subsequent removal from the transport module.
FR7521284A 1975-07-07 1975-07-07 Transport module for elongated articles partic. nuclear fuel rods - holds these clamped during transport but releases them at the reception point automatically Granted FR2317127A1 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
FR7521284A FR2317127A1 (en) 1975-07-07 1975-07-07 Transport module for elongated articles partic. nuclear fuel rods - holds these clamped during transport but releases them at the reception point automatically

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR7521284A FR2317127A1 (en) 1975-07-07 1975-07-07 Transport module for elongated articles partic. nuclear fuel rods - holds these clamped during transport but releases them at the reception point automatically

Publications (2)

Publication Number Publication Date
FR2317127A1 true FR2317127A1 (en) 1977-02-04
FR2317127B1 FR2317127B1 (en) 1979-05-11

Family

ID=9157612

Family Applications (1)

Application Number Title Priority Date Filing Date
FR7521284A Granted FR2317127A1 (en) 1975-07-07 1975-07-07 Transport module for elongated articles partic. nuclear fuel rods - holds these clamped during transport but releases them at the reception point automatically

Country Status (1)

Country Link
FR (1) FR2317127A1 (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0005623A2 (en) * 1978-05-15 1979-11-28 Westinghouse Electric Corporation Storage container for holding spent nuclear fuel rods at a reactor site
US4474727A (en) * 1978-05-15 1984-10-02 Westinghouse Electric Corp. Arrangement for storing spent nuclear fuel rods at a reactor site

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
EP0005623A2 (en) * 1978-05-15 1979-11-28 Westinghouse Electric Corporation Storage container for holding spent nuclear fuel rods at a reactor site
FR2426315A1 (en) * 1978-05-15 1979-12-14 Westinghouse Electric Corp DEVICE FOR STORING EXHAUSTED FUEL ON THE SITE OF A NUCLEAR REACTOR
EP0005623A3 (en) * 1978-05-15 1980-04-16 Westinghouse Electric Corporation Arrangement for storing spent nuclear fuel rods at a reactor site
US4474727A (en) * 1978-05-15 1984-10-02 Westinghouse Electric Corp. Arrangement for storing spent nuclear fuel rods at a reactor site

Also Published As

Publication number Publication date
FR2317127B1 (en) 1979-05-11

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Legal Events

Date Code Title Description
ST Notification of lapse