KR100448876B1 - 원자력발전소의 비상급수 시스템 - Google Patents
원자력발전소의 비상급수 시스템 Download PDFInfo
- Publication number
- KR100448876B1 KR100448876B1 KR10-2001-0069865A KR20010069865A KR100448876B1 KR 100448876 B1 KR100448876 B1 KR 100448876B1 KR 20010069865 A KR20010069865 A KR 20010069865A KR 100448876 B1 KR100448876 B1 KR 100448876B1
- Authority
- KR
- South Korea
- Prior art keywords
- water supply
- supply system
- emergency water
- emergency
- power plant
- 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 - Fee Related
Links
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 158
- 239000002826 coolant Substances 0.000 abstract description 17
- 230000005855 radiation Effects 0.000 abstract description 8
- 230000005856 abnormality Effects 0.000 abstract description 2
- 230000007257 malfunction Effects 0.000 abstract description 2
- 239000000498 cooling water Substances 0.000 abstract 1
- 238000010795 Steam Flooding Methods 0.000 description 9
- 238000010586 diagram Methods 0.000 description 7
- 239000008400 supply water Substances 0.000 description 7
- 239000003758 nuclear fuel Substances 0.000 description 3
- 238000001816 cooling Methods 0.000 description 2
- 239000000446 fuel Substances 0.000 description 2
- 230000000903 blocking effect Effects 0.000 description 1
- 230000007774 longterm Effects 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- 230000001105 regulatory effect Effects 0.000 description 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
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
-
- 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
Description
Claims (5)
- 삭제
- 삭제
- 원자력발전소에 필요한 급수를 저장하여 공급하는 비상급수탱크(30.34)와; 상기 비상급수탱크(30.34)에서 급수를 공급 받아 증기발생기(32.36)로 제공하는 급수계통(31.35) 및; 상기 비상급수탱크(30.34)와 상기 급수계통(31.35)으로부터 비상급수를 공급받는 증기발생기(32.36)로 이루어진 원자력발전소의 급수시스템에 있어서,상기 급수계통(31.35)에 각각 구비된 전동기구동펌프(20)와 증기구동펌프(22)가 각각의 배관연결점(42.43)을 통해 상호 연결되면서, 상기 배관연결점(42. 43)이 상호연결배관(44)을 통해 상호 연결되고, 상기 상호연결배관(44)에 밸브(41)를 통해 디젤구동펌프(40)가 연결되어,상기 급수시스템에 고장이 발생되는 경우 상기 디젤구동펌프(40)의 밸브(41)에 연결된 상기 상호연결배관(44)을 통해 상기 급수계통(31) 또는 급수계통(35)의 비상급수를 증기발생기(32.36)로 공급하는 것을 특징으로 하는 원자력발전소의 비상급수 시스템.
- 삭제
- 삭제
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
KR10-2001-0069865A KR100448876B1 (ko) | 2001-11-09 | 2001-11-09 | 원자력발전소의 비상급수 시스템 |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
KR10-2001-0069865A KR100448876B1 (ko) | 2001-11-09 | 2001-11-09 | 원자력발전소의 비상급수 시스템 |
Publications (2)
Publication Number | Publication Date |
---|---|
KR20030039062A KR20030039062A (ko) | 2003-05-17 |
KR100448876B1 true KR100448876B1 (ko) | 2004-09-18 |
Family
ID=29568813
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
KR10-2001-0069865A Expired - Fee Related KR100448876B1 (ko) | 2001-11-09 | 2001-11-09 | 원자력발전소의 비상급수 시스템 |
Country Status (1)
Country | Link |
---|---|
KR (1) | KR100448876B1 (ko) |
Families Citing this family (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
KR101234570B1 (ko) * | 2011-09-19 | 2013-02-19 | 한국원자력연구원 | 냉각재 상실사고 완화가 가능한 일체형 원자로 및 그 완화방법 |
KR20160003006U (ko) | 2015-02-24 | 2016-09-01 | 김흥일 | 비상발전기 냉각용 물순환 시스템 |
KR102572242B1 (ko) * | 2020-12-30 | 2023-08-29 | 한국수력원자력 주식회사 | 증기발생기의 냉각재 계통 및 원자력 발전소의 중대 사고 시 증기발생기에 냉각재를 공급하는 방법 |
Citations (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4654190A (en) * | 1984-04-05 | 1987-03-31 | Westinghouse Electric Corp. | Emergency feedwater system for steam generators of a nuclear power plant |
US4666662A (en) * | 1984-07-10 | 1987-05-19 | Westinghouse Electric Corp. | Steam generator recirculating system for a pressurized water nuclear reactor |
KR20010076565A (ko) * | 2000-01-26 | 2001-08-16 | 이종훈 | 원자력 발전소의 피동이차응축시스템 |
-
2001
- 2001-11-09 KR KR10-2001-0069865A patent/KR100448876B1/ko not_active Expired - Fee Related
Patent Citations (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4654190A (en) * | 1984-04-05 | 1987-03-31 | Westinghouse Electric Corp. | Emergency feedwater system for steam generators of a nuclear power plant |
US4666662A (en) * | 1984-07-10 | 1987-05-19 | Westinghouse Electric Corp. | Steam generator recirculating system for a pressurized water nuclear reactor |
KR20010076565A (ko) * | 2000-01-26 | 2001-08-16 | 이종훈 | 원자력 발전소의 피동이차응축시스템 |
Also Published As
Publication number | Publication date |
---|---|
KR20030039062A (ko) | 2003-05-17 |
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