GB1525020A - Removal of decay heat on failure of a pressurised-water reactor - Google Patents
Removal of decay heat on failure of a pressurised-water reactorInfo
- Publication number
- GB1525020A GB1525020A GB51269/75A GB5126975A GB1525020A GB 1525020 A GB1525020 A GB 1525020A GB 51269/75 A GB51269/75 A GB 51269/75A GB 5126975 A GB5126975 A GB 5126975A GB 1525020 A GB1525020 A GB 1525020A
- Authority
- GB
- United Kingdom
- Prior art keywords
- steam generator
- steam
- failure
- emergency
- main
- 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
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title 1
- 238000011109 contamination Methods 0.000 abstract 1
- 230000002285 radioactive effect Effects 0.000 abstract 1
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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
- G21D3/06—Safety arrangements responsive to faults within the plant
-
- 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
-
- 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)
- Business, Economics & Management (AREA)
- Emergency Management (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
In the event of operating leaks from the primary to the secondary side in the steam generator (5), of the failure of the main heat sink and/or of breakage of the main steam pipe, the amount of afterheat and steam still produced after shutdown of the reactor (3) is condensed using an emergency circuit (13, 14, 15, 16, 17) and the condensate is resupplied to the steam generator. The emergency circuit is connected via a controllable pressure-reducing valve (10) to the main steam pipes (7), which are connected to the steam generator. It has, inter alia, an afterheat removal heat exchanger (13) with an additional condensate cooler (17), and is connected to the steam generator (5) via an emergency feedwater pump (14), an emergency feedwater control valve (15) and a connecting piece (16). As a result, radioactive contamination of the environment is prevented even in the event of leaks in the steam generator. <IMAGE>
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE2459150A DE2459150C3 (en) | 1974-12-14 | 1974-12-14 | Method and circuit arrangement for removing the decay heat of a pressurized water reactor in the event of a malfunction |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1525020A true GB1525020A (en) | 1978-09-20 |
Family
ID=5933382
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB51269/75A Expired GB1525020A (en) | 1974-12-14 | 1975-12-15 | Removal of decay heat on failure of a pressurised-water reactor |
Country Status (5)
Country | Link |
---|---|
AT (1) | AT380119B (en) |
CH (1) | CH618805A5 (en) |
DE (1) | DE2459150C3 (en) |
FR (1) | FR2294517A1 (en) |
GB (1) | GB1525020A (en) |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5428652A (en) * | 1991-08-12 | 1995-06-27 | Siemens Aktiengesellschaft | Secondary-side residual-heat removal system for pressurized-water nuclear reactors |
US8647582B2 (en) | 2007-12-27 | 2014-02-11 | Elcon Recycling Center (2003) Ltd. | System for safely processing a fluid via monitoring and decreasing explosiveness |
CN104952495A (en) * | 2015-06-26 | 2015-09-30 | 上海核工程研究设计院 | Secondary side residual heat removal system for twin-reactor nuclear power plant |
Families Citing this family (9)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE2700168C3 (en) * | 1977-01-04 | 1981-11-12 | Kraftwerk Union AG, 4330 Mülheim | Device for the removal of decay heat in a steam power plant heated with nuclear energy |
DE2809466C3 (en) * | 1978-03-04 | 1986-05-28 | Brown Boveri Reaktor GmbH, 6800 Mannheim | Device for emergency cooling of a steam generator in a nuclear power plant |
DE2842875C2 (en) * | 1978-10-02 | 1984-01-12 | Brown Boveri Reaktor GmbH, 6800 Mannheim | Process and device for removing residual heat from a water-cooled nuclear reactor plant |
DE2921694C2 (en) * | 1979-05-29 | 1981-12-03 | Babcock-Brown Boveri Reaktor Gmbh, 6800 Mannheim | Device for removing the heat to be transferred in a steam generator of a pressurized water reactor system in the event of a brief failure of the emergency feed water pumps |
FR2487563A1 (en) * | 1980-07-25 | 1982-01-29 | Framatome Sa | METHOD AND DEVICE FOR COOLING EMERGENCY RESPONSE OF A NUCLEAR REACTOR |
FR2515853A1 (en) * | 1981-11-05 | 1983-05-06 | Framatome Sa | COOLING DEVICE FOR THE PRIMARY CIRCUIT OF A PRESSURE WATER NUCLEAR REACTOR |
DE3248029C2 (en) * | 1982-12-24 | 1987-04-09 | Brown Boveri Reaktor GmbH, 6800 Mannheim | Method for preventing consequential damage in the event of leaks occurring within a steam generator of a pressurized water reactor plant between the primary and secondary circuits |
EP0362596B1 (en) * | 1988-09-30 | 1993-12-01 | Siemens Aktiengesellschaft | Heat reactor system comprising a residual heat removal system and its use in boiling-water and pressurized-water reactors |
DE4126630A1 (en) * | 1991-08-12 | 1993-02-18 | Siemens Ag | SECOND-SIDED HEAT EXHAUST SYSTEM FOR PRESSURE WATER CORE REACTORS |
Family Cites Families (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR1290703A (en) * | 1960-06-01 | 1962-04-13 | Atomic Energy Authority Uk | Steam generator installation powered by a nuclear reactor |
FR1345085A (en) * | 1962-10-24 | 1963-12-06 | Cup safety device, especially for baby cups | |
GB1291706A (en) * | 1969-01-16 | 1972-10-04 | Atomic Energy Authority Uk | Improvements in nuclear reactors |
GB1297951A (en) * | 1969-04-14 | 1972-11-29 | ||
BE795482A (en) * | 1972-02-19 | 1973-05-29 | Siemens Ag | NUCLEAR REACTOR COOLING SYSTEM |
DE2336146A1 (en) * | 1973-07-16 | 1975-02-06 | Kraftwerk Union Ag | Compact V-form pressurised auxiliary condensers - dissipating excess steam and decay heat in PWR power plant |
-
1974
- 1974-12-14 DE DE2459150A patent/DE2459150C3/en not_active Expired
-
1975
- 1975-10-27 CH CH1386975A patent/CH618805A5/en not_active IP Right Cessation
- 1975-12-05 AT AT0930175A patent/AT380119B/en not_active IP Right Cessation
- 1975-12-12 FR FR7538217A patent/FR2294517A1/en active Granted
- 1975-12-15 GB GB51269/75A patent/GB1525020A/en not_active Expired
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5428652A (en) * | 1991-08-12 | 1995-06-27 | Siemens Aktiengesellschaft | Secondary-side residual-heat removal system for pressurized-water nuclear reactors |
US8647582B2 (en) | 2007-12-27 | 2014-02-11 | Elcon Recycling Center (2003) Ltd. | System for safely processing a fluid via monitoring and decreasing explosiveness |
US8920738B2 (en) | 2007-12-27 | 2014-12-30 | Elcon Recycling Center (2003) Ltd. | Method for safely processing a fluid via monitoring and decreasing explosiveness |
CN104952495A (en) * | 2015-06-26 | 2015-09-30 | 上海核工程研究设计院 | Secondary side residual heat removal system for twin-reactor nuclear power plant |
Also Published As
Publication number | Publication date |
---|---|
ATA930175A (en) | 1980-02-15 |
AT380119B (en) | 1986-04-10 |
FR2294517B1 (en) | 1981-08-28 |
DE2459150C3 (en) | 1988-07-07 |
DE2459150B2 (en) | 1980-07-03 |
FR2294517A1 (en) | 1976-07-09 |
CH618805A5 (en) | 1980-08-15 |
DE2459150A1 (en) | 1976-06-16 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
PS | Patent sealed [section 19, patents act 1949] | ||
PCNP | Patent ceased through non-payment of renewal fee |