GB1528012A - Nuclear reactor refuelling system - Google Patents
Nuclear reactor refuelling systemInfo
- Publication number
- GB1528012A GB1528012A GB28532/75A GB2853275A GB1528012A GB 1528012 A GB1528012 A GB 1528012A GB 28532/75 A GB28532/75 A GB 28532/75A GB 2853275 A GB2853275 A GB 2853275A GB 1528012 A GB1528012 A GB 1528012A
- Authority
- GB
- United Kingdom
- Prior art keywords
- bucket
- rails
- pair
- duct
- ramp means
- 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
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
- G21C19/32—Apparatus for removing radioactive objects or materials from the reactor discharge area, e.g. to a storage place; Apparatus for handling radioactive objects or materials within a storage place or removing them therefrom
-
- 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)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
1528012 Fuelling reactors UNITED KING- DOM ATOMIC ENERGY AUTHORITY 7 June 1976 [7 July 1975] 28532/75 Heading G6C A handling system for fuel element assemblies of a liquid metal cooled nuclear reactor comprises a transfer bucket and ramp means for guiding the bucket for lifting or lowering in a direction inclined to the vertical, a branch of the ramp means causing a change of attitude of the bucket between parallelism with the ramp means and a vertical attitude. As shown, the ramp means comprises two pairs of inclined parallel rails 10, 11 (only one rail of each pair being shown), the inner pair 11 having a branch in the lower end region which is inclined at a steeper angle than the parent rails, and the transfer bucket 2 has two longitudinally spaced pairs of trunnions 6, 7 of which the upper pair 6 are in engagement with the outer rails 10 whilst the lower pair 7 project less than the upper pair 6 so that they are capable of engaging only the inner rails 11. At the exchange position 1, a fuel element assembly can be manipulated by a charge/discharge machine (not shown) into and out of the transfer bucket 2 within a pool 4 of molten sodium, the upper end of which bucket 2 abuts a pad 8 on the vertical surface 3 of the reactor core vessel whilst its tapering lower end 5 fits within a socket 9. The interior of the socket 9 tapers in complementary manner to the lower end 5 of the bucket 2 and provides an opening 13 at its upper end which is wider than the bucket 2. The socket 9 is mounted on a shock absorber 12, which absorbs energy should a fuel element assembly be inadvertently dropped into the bucket 2, or should the bucket 2 be released inadvertently to run out of control down the rails 10, 11. The bucket 2 may be drawn along the rails 10, 11 by a chain drive (not shown) extending parallel with the rails 10, 11 and attached to the trunnions 6. Although not shown in the drawing, the upper region of a duct 14 housing the rails 10, 11 is surrounded by an annular coaxial duct whereby argon cooling gas can be passed through the inner duct 14 in heat exchange with the bucket 2 and returned through the outer duct to gas circulating means situated outside the reactor vault.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB28532/75A GB1528012A (en) | 1976-06-07 | 1976-06-07 | Nuclear reactor refuelling system |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB28532/75A GB1528012A (en) | 1976-06-07 | 1976-06-07 | Nuclear reactor refuelling system |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1528012A true GB1528012A (en) | 1978-10-11 |
Family
ID=10277129
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB28532/75A Expired GB1528012A (en) | 1976-06-07 | 1976-06-07 | Nuclear reactor refuelling system |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB1528012A (en) |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB2147137A (en) * | 1983-09-23 | 1985-05-01 | Westinghouse Electric Corp | Fuel transfer system upender using translation drive |
FR2993091A1 (en) * | 2012-07-05 | 2014-01-10 | Commissariat Energie Atomique | Installation unit for handling worn out fuel assemblies of sodium-cooled nuclear reactor vessel of nuclear power plant, has transfer unit transferring container to truck in transfer position when another truck is in extraction position |
CN106504806A (en) * | 2016-12-29 | 2017-03-15 | 中广核研究院有限公司 | A kind of soft drive and emergency trip device |
-
1976
- 1976-06-07 GB GB28532/75A patent/GB1528012A/en not_active Expired
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB2147137A (en) * | 1983-09-23 | 1985-05-01 | Westinghouse Electric Corp | Fuel transfer system upender using translation drive |
US4717531A (en) * | 1983-09-23 | 1988-01-05 | Westinghouse Electric Corp. | Fuel transfer system upender using translation drive |
FR2993091A1 (en) * | 2012-07-05 | 2014-01-10 | Commissariat Energie Atomique | Installation unit for handling worn out fuel assemblies of sodium-cooled nuclear reactor vessel of nuclear power plant, has transfer unit transferring container to truck in transfer position when another truck is in extraction position |
CN106504806A (en) * | 2016-12-29 | 2017-03-15 | 中广核研究院有限公司 | A kind of soft drive and emergency trip device |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
US2992174A (en) | Breeder-converter reactor | |
US3629062A (en) | Transfer machine for nuclear reactor | |
US4050986A (en) | Nuclear reactor I | |
US3600277A (en) | Refueling apparatus and method for fast reactors | |
US3354041A (en) | Nuclear reactor refuelling device | |
US3132998A (en) | Nuclear reactors | |
US4663114A (en) | Apparatus for handling nuclear fuel assemblies and assembly adapted to such an apparatus | |
GB1528012A (en) | Nuclear reactor refuelling system | |
US2886503A (en) | Jacketed fuel elements for graphite moderated reactors | |
GB849277A (en) | Improvements in nuclear reactors | |
US2936277A (en) | Reactor control system | |
GB1148154A (en) | Refuelling apparatus for a nuclear reactor | |
US3048532A (en) | Cruciform control rod joint | |
GB1472477A (en) | Nuclear reactor installations | |
US3208915A (en) | Pressure tube neutronic reactor | |
US3361635A (en) | Nuclear reactor control rod winding arrangements | |
GB1117265A (en) | A fuel charging installation for a nuclear reactor | |
US4705661A (en) | Fast neutron nuclear reactor equipped with a central handling cell and a boxed slab | |
GB1528272A (en) | Nuclear reactors | |
GB942277A (en) | Nuclear reactor fuel element changing arrangements | |
US3194741A (en) | Nuclear reactor fuelling apparatus | |
Hopkins | Nuclear reactor refuelling system | |
US3140238A (en) | Charging and service machine for gas-cooled reactors | |
GB1064382A (en) | Device for regulating the power of a nuclear reactor | |
US4332030A (en) | Paired absorber elements for gas cooled high temperature reactors |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
PS | Patent sealed | ||
PCNP | Patent ceased through non-payment of renewal fee |