JPS6119956B2 - - Google Patents
Info
- Publication number
- JPS6119956B2 JPS6119956B2 JP53061719A JP6171978A JPS6119956B2 JP S6119956 B2 JPS6119956 B2 JP S6119956B2 JP 53061719 A JP53061719 A JP 53061719A JP 6171978 A JP6171978 A JP 6171978A JP S6119956 B2 JPS6119956 B2 JP S6119956B2
- Authority
- JP
- Japan
- Prior art keywords
- seawater
- emergency auxiliary
- auxiliary equipment
- building
- cooling
- 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
- 239000013535 sea water Substances 0.000 claims description 61
- 238000001816 cooling Methods 0.000 claims description 44
- 238000000034 method Methods 0.000 description 15
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 15
- 238000010276 construction Methods 0.000 description 5
- 238000010586 diagram Methods 0.000 description 3
- 239000000498 cooling water Substances 0.000 description 2
- 239000013505 freshwater Substances 0.000 description 2
- 239000011435 rock Substances 0.000 description 2
- 230000005540 biological transmission Effects 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 230000006378 damage Effects 0.000 description 1
- 238000006073 displacement reaction Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000004576 sand Substances 0.000 description 1
- 239000007921 spray Substances 0.000 description 1
- 239000013589 supplement Substances 0.000 description 1
Classifications
-
- 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
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Description
【発明の詳細な説明】
本発明は原子力発電所における非常用補機冷却
海水系に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to an emergency auxiliary equipment cooling seawater system in a nuclear power plant.
非常用補機冷却海水系は原子炉事故時または原
子炉停止時等に作動する非常用補機設備の熱を除
去する非常用補機冷却系を熱交換器を介して冷却
するための系統である。以下第１図を参照して従
来の非常用補機冷却海水系の説明を行う。第１図
のうち破線で示した部分が非常用補機冷却系２３
でありその熱を除去するための非常用補機冷却系
２３の熱交換器１に冷却海水を送る系統が実線で
示す非常用補機冷却海水系２４である。非常用補
機冷却海水系２４は海水の水源１１より非常用補
機冷却海水ポンプ２で海水導入配管３を通じて熱
交換器１に冷却海水を送り、非常用補機冷却系２
３を冷却した後海水導出配管４を通じて放水口１
２へ放出する系統であつて、大地震時にも確実に
熱交換器に冷却海水を供給し、通過させ冷却でき
なければならない。 The emergency auxiliary equipment cooling seawater system is a system that cools the emergency auxiliary equipment cooling system, which removes heat from the emergency auxiliary equipment that operates in the event of a reactor accident or shutdown, through a heat exchanger. be. The conventional emergency auxiliary equipment cooling seawater system will be explained below with reference to FIG. The part indicated by the broken line in Figure 1 is the emergency auxiliary cooling system 23.
The system that sends cooling seawater to the heat exchanger 1 of the emergency auxiliary cooling system 23 for removing the heat is the emergency auxiliary cooling seawater system 24 shown by the solid line. The emergency auxiliary equipment cooling seawater system 24 sends cooling seawater from the seawater source 11 to the heat exchanger 1 through the seawater introduction pipe 3 with the emergency auxiliary equipment cooling seawater pump 2, and the emergency auxiliary equipment cooling system 2
After cooling the water outlet 1 through the seawater outlet pipe 4
The system must be able to reliably supply cooling seawater to the heat exchanger and cool it by passing it through, even in the event of a major earthquake.
従来、原子力発電所の建屋５１外配管の支持方
法としては、第２図のように海水導出配管４を直
接地表３１上に配置する方法、第３図のように海
水導出配管４を適切な架台４１を介して地表３１
上に配置する方法、第４図のように地中に大径の
配管４４を埋設、この配管４４内に架台４２を介
して支持する方法、第５図のように人工岩４６を
直接岩盤３２上に設置し、この人工岩４６上にコ
ンクリート製ダクト４５を設け、このダクト４５
内に架台４３を介して支持する方法などによつて
施されている。 Conventionally, methods for supporting the piping outside the building 51 of a nuclear power plant include placing the seawater outlet piping 4 directly on the ground surface 31 as shown in Figure 2, and placing the seawater outlet piping 4 on an appropriate mount as shown in Figure 3. 41 to surface 31
A method in which a large-diameter pipe 44 is buried underground as shown in FIG. A concrete duct 45 is installed on this artificial rock 46, and this duct 45
This is carried out by a method of supporting the frame 43 inside the frame 43.
しかし、第２図、第３図および第４図で示され
た方法の場合、大地震時には、土砂の相対変位に
よつて海水導出配管４に過大な変形を生じて、あ
るいは埋設配管の破壊による土圧によつて海水導
出配管４が閉塞するおそれがある。 However, in the case of the methods shown in Figures 2, 3, and 4, in the event of a large earthquake, the seawater outlet pipe 4 may be excessively deformed due to the relative displacement of earth and sand, or the buried pipe may be destroyed. There is a risk that the seawater outlet pipe 4 may become clogged due to earth pressure.
なお建屋内の海水導出配管は建屋内架台（図示
せず）等により支持されており、大地震時等に破
壊される恐れはほとんどない。 The seawater outlet piping inside the building is supported by a frame (not shown) inside the building, so there is little risk of it being destroyed in the event of a major earthquake.
一方第５図で示された方法の場合は、直接岩盤
３２と人工岩４６によつて支持されるので、海水
導出配管４に過大な変形を生じることがなく、ま
た充分な強度を持つコンクリート製ダクト４５に
格納することによつて土圧が直接に海水導出配管
４にかかることも無いが、ダクト４５を含めて建
設工程が長くなる。 On the other hand, in the case of the method shown in FIG. 5, since the seawater outlet pipe 4 is directly supported by the bedrock 32 and the artificial rock 46, excessive deformation does not occur in the seawater outlet pipe 4, and the pipe is made of concrete with sufficient strength. Although the earth pressure is not directly applied to the seawater outlet pipe 4 by storing it in the duct 45, the construction process including the duct 45 becomes longer.
本発明は、上記の非常用補機冷却海水系２４の
海水導出配管４の建設工程の短縮、安全性および
耐震性をさらに増すために、建屋５１外の海水導
出配管４が閉塞した場合にも、非常用補機の冷却
という機能の維持ができる原子力発電所の配管の
耐震安全装置（以下非常用放水装置という）を提
供するものである。すなわち、第１の目的とする
ところは、非常用補機冷却系２３の熱交換器１を
格納する建屋５１外の海水導出配管４の支持方法
に関係なく、非常用補機冷却系２３の機能を維持
し、信頼性および耐震性をさらに増すことができ
る配管の非常用放水装置を得ることにある。次に
第２の目的とするところは、数十ｍもある建屋５
１外の海水導出配管４の配管等の支持方法を簡単
にして、建設工程の短縮をはかることにある。 In order to further shorten the construction process of the seawater outlet pipe 4 of the emergency auxiliary equipment cooling seawater system 24, and further increase safety and earthquake resistance, the present invention provides a system that can be used even when the seawater outlet pipe 4 outside the building 51 is blocked. , provides an earthquake-resistant safety device for nuclear power plant piping (hereinafter referred to as an emergency water discharge device) that can maintain the function of cooling emergency auxiliary equipment. That is, the first objective is to improve the function of the emergency auxiliary cooling system 23 regardless of the method of supporting the seawater outlet pipe 4 outside the building 51 that houses the heat exchanger 1 of the emergency auxiliary cooling system 23. The objective is to obtain an emergency water discharge system for piping that can maintain the water quality and further increase reliability and earthquake resistance. Next, the second objective is the building 5, which is several tens of meters long.
The purpose is to shorten the construction process by simplifying the method of supporting piping, etc. for the seawater outlet piping 4.
以下図面を参照して本発明の一実施例を説明す
る。第６図は、本発明の適用場所を示すものであ
る。この図からわかるように、配管の非常用放水
装置１０１を非常用補機冷却系２３の熱交換器１
を格納する建屋５１内から建屋壁５２の外部付近
にわたり設置するものである。非常用補機冷却海
水系２４は、原子炉事故時または原子炉停止時等
に作動するものである。非常用補機２１より伝達
される熱は、非常用補機冷却系２３のポンプ２２
によつて循環する淡水冷却水により冷却され、更
に熱交換器１を介して非常用補機冷却海水系２４
に伝達除去される。非常用補機冷却海水系２４は
ポンプ２により水源１１から海水導入配管３を通
じて熱交換器１に冷却海水を送り込み、この冷却
海水は熱交換器１で熱を受け、海水導出配管４を
通して放水口１２に放出する。非常用補機冷却海
水系２４の海水導出配管４には、本発明の非常用
放水装置１０１が設置されており、その実施例を
第７図に示す。この図からわかるように非常用補
機冷却海水系２４の建屋５１内の海水導出配管４
に建屋５１外に開口をす分岐放出管５を設置し、
この分岐放出管５に設定圧力以上で管路が開く破
壊板１２１を設置し、海水を建屋５１外に放出す
るものである。 An embodiment of the present invention will be described below with reference to the drawings. FIG. 6 shows where the present invention is applied. As can be seen from this figure, the emergency water discharge device 101 of the piping is connected to the heat exchanger 1 of the emergency auxiliary equipment cooling system 23.
It is installed from the inside of the building 51 where the equipment is stored to near the outside of the building wall 52. The emergency auxiliary equipment cooling seawater system 24 is operated in the event of a nuclear reactor accident or nuclear reactor shutdown. The heat transferred from the emergency auxiliary equipment 21 is transferred to the pump 22 of the emergency auxiliary equipment cooling system 23.
The system is cooled by freshwater cooling water circulated by
transmission is removed. The emergency auxiliary equipment cooling seawater system 24 uses a pump 2 to send cooling seawater from a water source 11 to a heat exchanger 1 through a seawater inlet pipe 3, and this cooling seawater receives heat in the heat exchanger 1 and passes through a seawater outlet pipe 4 to a water outlet. Released on 12th. An emergency water discharge device 101 of the present invention is installed in the seawater outlet pipe 4 of the emergency auxiliary equipment cooling seawater system 24, and an embodiment thereof is shown in FIG. As can be seen from this figure, the seawater outlet pipe 4 in the building 51 of the emergency auxiliary equipment cooling seawater system 24
A branch discharge pipe 5 having an opening outside the building 51 is installed,
A break plate 121 is installed in this branch discharge pipe 5 so that the pipe opens when the pressure exceeds a set pressure, and seawater is discharged to the outside of the building 51.
次に作用を説明する。非常用補機冷却海水系２
４は、原子炉事故時または原子炉停止時等に作動
し、原子炉等で発生する熱負荷は非常用補機２１
を通じて非常用補機冷却系２３ポンプ２２を運転
することによつて、熱交換器１を介して、熱を非
常用補機冷却海水系２４に伝えて除熱し、放水口
１２に放出する。 Next, the action will be explained. Emergency auxiliary equipment cooling seawater system 2
4 is activated in the event of a nuclear reactor accident or nuclear reactor shutdown, etc., and the heat load generated in the reactor etc. is handled by the emergency auxiliary equipment 21.
By operating the pump 22 of the emergency auxiliary cooling system 23 through the heat exchanger 1, heat is transferred to the emergency auxiliary cooling seawater system 24, where the heat is removed, and the heat is discharged to the water outlet 12.
しかし、前記海水導出配管４が第５図のように
強固な支持方法で支持されていない場合には、大
地震時、前記海水導出配管４は建屋５１の外で閉
塞する可能性がある。（なお非常用補機冷却海水
系の海水導入配管３は第５図のように大地震時に
も建全性が保たれる構造となつている。）このよ
うな建屋外の海水導出配管４の閉塞時に、海水導
出配管４の圧力はポンプ２のポンプ特性曲線によ
つて高くなり破壊板１２１が破れると冷却水は分
岐放出管５を通して建屋５１外に放出される。よ
つて非常用補機冷却海水系２４を通水継続運転す
ることが可能となり、原子炉等で発生する熱負荷
の除去ができる。なお分岐放出管５から放出され
る海水は建屋の外に流れ出るが、原子力発電所の
機能にほとんど影響はない。また本願の分岐放出
管５は地震等により破損する確率が小さい建屋内
の海水導出配管４から分岐されているため安全性
が高い。即ち非常用補機冷却系２３および非常用
補機冷却海水系２４の信頼性および耐震性を増す
ことができ、その結果原子力発電所の安全性を高
める。 However, if the seawater outlet pipe 4 is not supported by a strong support method as shown in FIG. 5, the seawater outlet pipe 4 may become blocked outside the building 51 in the event of a major earthquake. (As shown in Figure 5, the seawater inlet piping 3 of the emergency auxiliary equipment cooling seawater system has a structure that maintains its integrity even in the event of a major earthquake.) At the time of blockage, the pressure in the seawater outlet pipe 4 increases according to the pump characteristic curve of the pump 2, and when the rupture plate 121 ruptures, the cooling water is discharged to the outside of the building 51 through the branch discharge pipe 5. Therefore, the emergency auxiliary equipment cooling seawater system 24 can continue to be operated with water flowing through it, and the heat load generated in the nuclear reactor or the like can be removed. Although the seawater released from the branch discharge pipe 5 flows out of the building, it has almost no effect on the functions of the nuclear power plant. Further, the branch discharge pipe 5 of the present application is highly safe because it is branched from the seawater outlet pipe 4 inside the building, which has a low probability of being damaged by earthquakes or the like. That is, the reliability and earthquake resistance of the emergency auxiliary cooling system 23 and the emergency auxiliary cooling seawater system 24 can be increased, and as a result, the safety of the nuclear power plant is improved.
また、海水導出配管４の建屋５１の外での配管
の支持方法が簡易なものですむため、建設工程の
短縮をはかることができる。 Further, since the method of supporting the seawater outlet piping 4 outside the building 51 is simple, the construction process can be shortened.
以上説明のように本発明は構成されているた
め、大地震時に建屋外の海水導出配管に閉塞が生
じたとしても非常用補機冷却系２３および非常用
補機冷却海水系２４は連続通水運転が可能とな
り、信頼性および耐震性を更に増すことができ
る。また屋外での配管支持方法が簡単になるため
建設工程の短縮をはかることができる。 Since the present invention is constructed as described above, even if a blockage occurs in the seawater outlet piping outside the building during a major earthquake, the emergency auxiliary equipment cooling system 23 and the emergency auxiliary equipment cooling seawater system 24 will continue to have water flow. It becomes possible to operate the system, and further increases reliability and earthquake resistance. Furthermore, since the method of supporting the pipes outdoors is simplified, the construction process can be shortened.
なお、前述の如く水源１１は海水だけでなく淡
水でも同様となる。 Note that, as described above, the water source 11 can be not only seawater but also freshwater.
第１図は従来の非常用補機冷却系及び非常用補
機冷却海水系の概略系統構成を示す説明図、第２
図、第３図、第４図、第５図は従来の非常用補機
冷却海水系の建屋外での配管支持方法を説明する
ための断面図、第６図は本発明の配管の耐震安全
装置を設けた非常用補機冷却系および非常用補機
冷却海水系の概略系統構成を示す説明図、第７図
は本発明の実施例を示す系統構成図である。
１……熱交換器、２……ポンプ、３……海水導
入配管、４……海水導出配管、５……分岐放出
管、１１……水源、１２……放水口、２１……非
常用補機、２２……ポンプ、２３……非常用補機
冷却系、２４……非常用補機冷却海水系、３１…
…地表、１０１……非常用放水装置（耐震安全装
置）、１２１……破壊板。
Figure 1 is an explanatory diagram showing the schematic system configuration of a conventional emergency auxiliary equipment cooling system and emergency auxiliary equipment cooling seawater system.
Figures 3, 4, and 5 are cross-sectional views for explaining the conventional method of supporting piping outside the building of an emergency auxiliary cooling seawater system, and Figure 6 shows the seismic safety of piping according to the present invention. FIG. 7 is an explanatory diagram showing a schematic system configuration of an emergency auxiliary cooling system and an emergency auxiliary cooling seawater system provided with devices, and FIG. 7 is a system configuration diagram showing an embodiment of the present invention. 1...Heat exchanger, 2...Pump, 3...Seawater inlet piping, 4...Seawater outlet piping, 5...Branch discharge pipe, 11...Water source, 12...Water outlet, 21...Emergency supplement Machine, 22...Pump, 23...Emergency auxiliary cooling system, 24...Emergency auxiliary cooling seawater system, 31...
...Ground surface, 101...Emergency water spray device (earthquake safety device), 121...Destruction plate.
Claims (1)
機設備の熱を熱交換器を介して海水で冷却する非
常用補機冷却海水系において、前記熱交換器の建
屋内の海水導出配管から分岐して建屋外に開口す
る分岐放出管を設け、この分岐放出管に破壊板を
設けてなることを特徴とする非常用補機冷却海水
系。1. In the emergency auxiliary equipment cooling seawater system that cools the heat of the emergency auxiliary equipment installed in the building of a nuclear power plant with seawater via a heat exchanger, from the seawater outlet piping inside the building of the heat exchanger. An emergency auxiliary equipment cooling seawater system characterized by having a branch discharge pipe that branches out and opens outside the building, and a break plate provided on the branch discharge pipe.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP6171978A JPS54153996A (en) | 1978-05-25 | 1978-05-25 | Sub-cooling sea water system for emergency |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP6171978A JPS54153996A (en) | 1978-05-25 | 1978-05-25 | Sub-cooling sea water system for emergency |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS54153996A JPS54153996A (en) | 1979-12-04 |
| JPS6119956B2 true JPS6119956B2 (en) | 1986-05-20 |
Family
ID=13179303
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP6171978A Granted JPS54153996A (en) | 1978-05-25 | 1978-05-25 | Sub-cooling sea water system for emergency |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS54153996A (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP5188906B2 (en) * | 2008-08-07 | 2013-04-24 | 日立Ｇｅニュークリア・エナジー株式会社 | Anomaly detection equipment for nuclear power plants |
| JP6806445B2 (en) * | 2016-01-18 | 2021-01-06 | 三菱重工業株式会社 | Piping support structure and its formation method |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5117799A (en) * | 1974-06-26 | 1976-02-12 | Kraftwerk Union Ag |
-
1978
- 1978-05-25 JP JP6171978A patent/JPS54153996A/en active Granted
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5117799A (en) * | 1974-06-26 | 1976-02-12 | Kraftwerk Union Ag |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS54153996A (en) | 1979-12-04 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US4971752A (en) | Safety design for nuclear power plants | |
| EP2096644B1 (en) | Passive cooling and depressurization system and pressurized water nuclear power plant | |
| KR102020908B1 (en) | Main steam system that reduces the release of radioactive material to the atmosphere under severe accident | |
| US4050983A (en) | Passive containment system | |
| US3168445A (en) | Safety equipment for nuclear powerreactor plants | |
| CA2968581C (en) | Containment vessel drain system | |
| JP2983290B2 (en) | Heat release equipment for nuclear reactors, especially pressurized water reactors | |
| JPS6184588A (en) | Underground type nuclear power plant | |
| JPS6119956B2 (en) | ||
| US20200234836A1 (en) | System and method for reducing atmospheric release of radioactive materials caused by severe accident | |
| KR102113284B1 (en) | system and a method for reducing the release of radioactive material to the atmosphere under severe accident | |
| US10446279B2 (en) | Boiling water type nuclear power plant | |
| JPS58193492A (en) | Emergency auxiliary machine cooling sea water system | |
| JP6277466B2 (en) | Nuclear power plant equipment. | |
| JPS58193493A (en) | Emergency auxiliary machine cooling sea water system | |
| JP6348855B2 (en) | Emergency core cooling system for nuclear power plants | |
| CN111063462B (en) | Self-generating cooling system after spent fuel pool accident | |
| JPH0450798A (en) | Emitted radiation reduction device | |
| JP3449583B2 (en) | Condensate storage equipment | |
| JP4974258B1 (en) | Nuclear power plant with radioactive decontamination facility | |
| KR101565547B1 (en) | Coping methods for extreme natural events in nuclear power plants | |
| RU2106025C1 (en) | Shielding system for water-moderated reactor containment | |
| JP2017219525A (en) | Device for preventing nuclear reactor from leaking radioactivity | |
| RU2093909C1 (en) | Nuclear power plant | |
| JPH02157699A (en) | Sea water collecting facility |