GB1148154A - Refuelling apparatus for a nuclear reactor - Google Patents
Refuelling apparatus for a nuclear reactorInfo
- Publication number
- GB1148154A GB1148154A GB813/68A GB81368A GB1148154A GB 1148154 A GB1148154 A GB 1148154A GB 813/68 A GB813/68 A GB 813/68A GB 81368 A GB81368 A GB 81368A GB 1148154 A GB1148154 A GB 1148154A
- Authority
- GB
- United Kingdom
- Prior art keywords
- carriage
- tube
- ramp
- fuel assembly
- station
- 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
- G21C19/18—Apparatus for bringing fuel elements to the reactor charge area, e.g. from a storage place
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
-
- 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
-
- 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)
- Carriers, Traveling Bodies, And Overhead Traveling Cranes (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
1,148,154. Fuelling reactors. COMMISSARIAT A L'ENERGIE ATOMIQUE. 5 Jan., 1968 [26 Jan., 1967], No. 813/68. Heading G6C. Fuelling apparatus for a fast reactor comprising a core 20 in a primary vessel 10 filled with molten sodium 12, includes a ramp B extending from a fuelling station 22 to a shielded lock chamber A receiving a switching tube 46 pivotally mounted at its upper end. The tube 46 may be moved from the Fig. 1 position in which it is aligned with the ramp B to an alternative position in which it is aligned with a ramp B<SP>1</SP> leading to a recovery station C. A carriage (Fig. 4, not shown) for receiving a fuel assembly is movable along the ramps B, B<SP>1</SP> and tube 46 by a hoist (Fig. 6, not shown) disposed in an enclosure 80. A jack in the enclosure 80 imparts a small axial motion to the tube 46 so that it may be coupled to or uncoupled from the ends of the ramps B, B<SP>1</SP> when it is pivoted about its upper end by means of a traverser 54 movable along rails 56. In operation, the fuel assembly carriage is lowered down ramp B<SP>1</SP> into the recovery station and a new fuel assembly is lowered through a valve 42 into the carriage, the latter then being raised into the tube 46. The tube 46 is aligned with ramp B and the carriage is lowered into fuelling station 22. A rotary arm 18 mounted in a rotary plug 16 removes the fuel assembly from the carriage and places the assembly in the core 20. A spent fuel assembly which has been previously removed from the core by the arm 18 and left to cool off in a store in the vessel 10 is now placed by the arm in the carriage and the latter is returned to the station C.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR92671A FR1525102A (en) | 1967-01-26 | 1967-01-26 | Fuel loading and unloading device for nuclear reactor |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1148154A true GB1148154A (en) | 1969-04-10 |
Family
ID=8624431
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB813/68A Expired GB1148154A (en) | 1967-01-26 | 1968-01-05 | Refuelling apparatus for a nuclear reactor |
Country Status (6)
Country | Link |
---|---|
BE (1) | BE708628A (en) |
CH (1) | CH485298A (en) |
ES (1) | ES349785A1 (en) |
FR (1) | FR1525102A (en) |
GB (1) | GB1148154A (en) |
LU (1) | LU55312A1 (en) |
Cited By (2)
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 |
CN113593737A (en) * | 2021-07-14 | 2021-11-02 | 中国科学院上海应用物理研究所 | Automatic discharging device |
Families Citing this family (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2188251B1 (en) * | 1972-06-08 | 1976-01-16 | Commissariat A En Atomique Fr | |
GB1528272A (en) * | 1976-01-07 | 1978-10-11 | Atomic Energy Authority Uk | Nuclear reactors |
US4069099A (en) * | 1976-02-23 | 1978-01-17 | Westinghouse Electric Corporation | Nuclear reactor fuel transfer system |
FR2410340A1 (en) * | 1977-11-29 | 1979-06-22 | Commissariat Energie Atomique | CLOSING DEVICE FOR AN ASSEMBLY HANDLING POT |
FR2486297A1 (en) * | 1980-07-01 | 1982-01-08 | Novatome | DEVICE FOR LOADING AND UNLOADING COMBUSTIBLE ASSEMBLIES FOR FAST NEUTRON NUCLEAR REACTOR |
FR2488719B1 (en) * | 1980-08-14 | 1985-10-04 | Commissariat Energie Atomique | INSTALLATION AND METHOD FOR HANDLING FAST NEUTRAL NUCLEAR REACTOR ASSEMBLIES |
RU2449390C1 (en) * | 2011-05-17 | 2012-04-27 | Открытое акционерное общество "Российский концерн по производству электрической и тепловой энергии на атомных станциях" (ОАО "Концерн "Росэнергоатом") | Track of process channel of nuclear uranium-graphite reactor |
-
1967
- 1967-01-26 FR FR92671A patent/FR1525102A/en not_active Expired
- 1967-12-28 BE BE708628D patent/BE708628A/xx not_active IP Right Cessation
-
1968
- 1968-01-03 CH CH2768A patent/CH485298A/en not_active IP Right Cessation
- 1968-01-05 GB GB813/68A patent/GB1148154A/en not_active Expired
- 1968-01-18 LU LU55312D patent/LU55312A1/xx unknown
- 1968-01-26 ES ES349785A patent/ES349785A1/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 |
CN113593737A (en) * | 2021-07-14 | 2021-11-02 | 中国科学院上海应用物理研究所 | Automatic discharging device |
CN113593737B (en) * | 2021-07-14 | 2024-03-08 | 中国科学院上海应用物理研究所 | Automatic discharging device |
Also Published As
Publication number | Publication date |
---|---|
CH485298A (en) | 1970-01-31 |
LU55312A1 (en) | 1968-03-30 |
BE708628A (en) | 1968-05-02 |
FR1525102A (en) | 1968-05-17 |
ES349785A1 (en) | 1969-11-01 |
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