GB1336716A - Emergency cooling system for a nuclear reactor - Google Patents
Emergency cooling system for a nuclear reactorInfo
- Publication number
- GB1336716A GB1336716A GB6281569A GB1336716DA GB1336716A GB 1336716 A GB1336716 A GB 1336716A GB 6281569 A GB6281569 A GB 6281569A GB 1336716D A GB1336716D A GB 1336716DA GB 1336716 A GB1336716 A GB 1336716A
- Authority
- GB
- United Kingdom
- Prior art keywords
- water
- heat
- circuit
- emergency
- pump
- 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
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
-
- 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
1336716 Nuclear power plant BRITISH NUCLEAR DESIGN & CONSTRUCTION Ltd and ENGLISH ELECTRIC CO Ltd 18 Dec 1970 [24 Dec 1969] 62815/69 Heading G6C The pressure vessel wall 4 of a gas-cooled reactor forming part of a direct-cycle gas turbine power plant accommodates a pre-cooler 2 and inter-cooler 3 which abstract heat from the gas coolant in its return passage from the turbine to the reactor core. The heat exchangers 2, 3 together with a heat exchanger 5 form an intermediate cooling circuit 1 through which water is circulated by a pump 8 through a non- return valve 9. Heat is abstracted from the circuit 1 by a further circuit 6 through which water is circulated by a further pump (not shown), the heat in circuit 6 being rejected to the sea or atmosphere. Should the power supply to the pumps fail, the water circulation practically ceases so that the water in the heat exchangers 2, 3 boils and at a certain pressure a safety valve 10 opens to vent the steam to atmosphere. At the same time a small pump 12, energized from an emergency source, is started to draw water from an emergency supply tank 11 to replace the loss through the valve 10. Thus the latent heat of vaporization of water is used to provide an emergency cooling system.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB6281569 | 1969-12-24 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1336716A true GB1336716A (en) | 1973-11-07 |
Family
ID=10488518
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB6281569A Expired GB1336716A (en) | 1969-12-24 | 1969-12-24 | Emergency cooling system for a nuclear reactor |
Country Status (4)
Country | Link |
---|---|
JP (1) | JPS5117677B1 (en) |
DE (1) | DE2062933A1 (en) |
FR (1) | FR2073493B1 (en) |
GB (1) | GB1336716A (en) |
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO2007116045A1 (en) * | 2006-04-12 | 2007-10-18 | Shell Internationale Research Maatschappij B.V. | Apparatus and process for cooling hot gas |
CN103206886A (en) * | 2013-03-28 | 2013-07-17 | 中国核电工程有限公司 | Strengthened heat exchange structure of heat exchange interface of water-cooled wall heat exchange tube |
FR2985842A1 (en) * | 2012-01-18 | 2013-07-19 | Technicatome | SYSTEM FOR EVACUATING THE RESIDUAL POWER OF A PRESSURIZED WATER NUCLEAR REACTOR |
CN109727688A (en) * | 2018-12-29 | 2019-05-07 | 福建福清核电有限公司 | Nuclear power plant's essential service water pump and follow pump emergency axle envelope water supply system and method |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN113539530B (en) * | 2021-07-05 | 2022-12-09 | 西安交通大学 | Emergency heat exporting system of solid-state reactor core nuclear reactor for deep sea underwater navigation and working method |
Family Cites Families (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR1308523A (en) * | 1961-12-27 | 1962-11-03 | Interatom | Nuclear reactor cooling installation for a ship |
-
1969
- 1969-12-24 GB GB6281569A patent/GB1336716A/en not_active Expired
-
1970
- 1970-12-21 DE DE19702062933 patent/DE2062933A1/en active Pending
- 1970-12-22 FR FR7046171A patent/FR2073493B1/fr not_active Expired
- 1970-12-24 JP JP45116857A patent/JPS5117677B1/ja active Pending
Cited By (8)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO2007116045A1 (en) * | 2006-04-12 | 2007-10-18 | Shell Internationale Research Maatschappij B.V. | Apparatus and process for cooling hot gas |
US7628121B2 (en) | 2006-04-12 | 2009-12-08 | Shell Oil Company | Apparatus and process for cooling hot gas |
FR2985842A1 (en) * | 2012-01-18 | 2013-07-19 | Technicatome | SYSTEM FOR EVACUATING THE RESIDUAL POWER OF A PRESSURIZED WATER NUCLEAR REACTOR |
WO2013107790A1 (en) * | 2012-01-18 | 2013-07-25 | Societe Technique Pour L'energie Atomique Technicatome | System for discharging the residual power of a pressurised water nuclear reactor |
US10255999B2 (en) | 2012-01-18 | 2019-04-09 | Societe Technique Pour L'energie Atomique Technicatome | System for removing the residual power of a pressurised water nuclear reactor |
CN103206886A (en) * | 2013-03-28 | 2013-07-17 | 中国核电工程有限公司 | Strengthened heat exchange structure of heat exchange interface of water-cooled wall heat exchange tube |
CN109727688A (en) * | 2018-12-29 | 2019-05-07 | 福建福清核电有限公司 | Nuclear power plant's essential service water pump and follow pump emergency axle envelope water supply system and method |
CN109727688B (en) * | 2018-12-29 | 2022-11-22 | 福建福清核电有限公司 | Important service water pump of nuclear power plant and circulating pump emergency shaft seal water supply system and method |
Also Published As
Publication number | Publication date |
---|---|
FR2073493A1 (en) | 1971-10-01 |
FR2073493B1 (en) | 1975-03-21 |
DE2062933A1 (en) | 1971-07-01 |
JPS5117677B1 (en) | 1976-06-03 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
PS | Patent sealed | ||
PLNP | Patent lapsed through nonpayment of renewal fees |