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 automaticallyInfo
- 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
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
- G21C19/02—Details of handling arrangements
- G21C19/06—Magazines for holding fuel elements or control elements
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B60—VEHICLES IN GENERAL
- B60P—VEHICLES ADAPTED FOR LOAD TRANSPORTATION OR TO TRANSPORT, TO CARRY, OR TO COMPRISE SPECIAL LOADS OR OBJECTS
- B60P3/00—Vehicles adapted to transport, to carry or to comprise special loads or objects
-
- 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
- G21C19/18—Apparatus for bringing fuel elements to the reactor charge area, e.g. from a storage place
-
- 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
- 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.
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)
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 |
-
1975
- 1975-07-07 FR FR7521284A patent/FR2317127A1/en active Granted
Non-Patent Citations (1)
Title |
---|
NEANT * |
Cited By (4)
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 |