JPH01161194A - Boric acid injecting device - Google Patents
Boric acid injecting deviceInfo
- Publication number
- JPH01161194A JPH01161194A JP62318654A JP31865487A JPH01161194A JP H01161194 A JPH01161194 A JP H01161194A JP 62318654 A JP62318654 A JP 62318654A JP 31865487 A JP31865487 A JP 31865487A JP H01161194 A JPH01161194 A JP H01161194A
- Authority
- JP
- Japan
- Prior art keywords
- pump
- reactor
- boric acid
- turbine
- piping
- 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.)
- Pending
Links
- KGBXLFKZBHKPEV-UHFFFAOYSA-N boric acid Chemical compound OB(O)O KGBXLFKZBHKPEV-UHFFFAOYSA-N 0.000 title claims abstract description 18
- 239000004327 boric acid Substances 0.000 title claims abstract description 18
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 45
- 238000002347 injection Methods 0.000 claims abstract description 31
- 239000007924 injection Substances 0.000 claims abstract description 31
- 230000001629 suppression Effects 0.000 abstract description 5
- 230000001105 regulatory effect Effects 0.000 abstract description 3
- 239000007921 spray Substances 0.000 description 7
- 238000001816 cooling Methods 0.000 description 6
- 238000002955 isolation Methods 0.000 description 5
- 238000006243 chemical reaction Methods 0.000 description 4
- 230000009193 crawling Effects 0.000 description 4
- 239000002253 acid Substances 0.000 description 3
- 238000010586 diagram Methods 0.000 description 3
- 239000000498 cooling water Substances 0.000 description 2
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 1
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 1
- 230000002159 abnormal effect Effects 0.000 description 1
- 238000010521 absorption reaction Methods 0.000 description 1
- 229910052796 boron Inorganic materials 0.000 description 1
- 230000001276 controlling effect Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000005484 gravity Effects 0.000 description 1
- 229910052739 hydrogen Inorganic materials 0.000 description 1
- 239000001257 hydrogen Substances 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 230000009257 reactivity Effects 0.000 description 1
- 230000001052 transient effect Effects 0.000 description 1
- 238000011144 upstream manufacturing Methods 0.000 description 1
Classifications
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F02—COMBUSTION ENGINES; HOT-GAS OR COMBUSTION-PRODUCT ENGINE PLANTS
- F02B—INTERNAL-COMBUSTION PISTON ENGINES; COMBUSTION ENGINES IN GENERAL
- F02B3/00—Engines characterised by air compression and subsequent fuel addition
- F02B3/06—Engines characterised by air compression and subsequent fuel addition with compression ignition
-
- 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)
Abstract
Description
【発明の詳細な説明】
（発明の目的）
（産業上の利用分野）
本発明は、原子炉停止系の１つであるほう酸水注入装置
に関り−る。DETAILED DESCRIPTION OF THE INVENTION (Objective of the Invention) (Industrial Application Field) The present invention relates to a boric acid water injection device which is one of the nuclear reactor shutdown systems.
（従来の技術）
従来のほう酸水注入装置を第３図に示づ。ほう酸水タン
クＡに接続された配管か仕切弁Ｂを介してポンプＣの吸
込側に接続される。ざらにポンプ○の吐出側から配管が
注入弁りを介して原子炉Ｆ−］−
へ接続される。ポンプＣ等は通常の電源が喪失した場合
にも注入が可能なようにするため、非常用ディーゼル発
電機（図示せず）等に接続されている。(Prior Art) A conventional boric acid water injection device is shown in FIG. The piping connected to the boric acid water tank A is connected to the suction side of the pump C via the gate valve B. Roughly, piping is connected from the discharge side of pump ○ to reactor F-]- via an injection valve. Pump C etc. are connected to an emergency diesel generator (not shown) etc. to enable injection even if the normal power source is lost.
原子炉は通常時制御棒を挿入して炉を停止することがで
き、さらに緊急時にはスクラムにより制御棒を急速挿入
することかできるが、万一、これらの手段による炉停止
かできないような場合には、はう酸水注入装置によりほ
う酸水を原子炉へ注入し、はう索による中性子吸収によ
り原子炉の核反応を停止することかできる。この場合、
ポンプＣを起動し、什切づ↑Ｂ及σ注入弁りを聞りるこ
とにより、ほう酸水タンク内のほう酸水を原子炉へ注入
覆る。Normally, a nuclear reactor can be shut down by inserting control rods, and in an emergency, control rods can be quickly inserted using a scram, but in the unlikely event that these methods cannot be used to shut down the reactor. By injecting boric acid water into the reactor using a crawling acid water injection device, it is possible to stop the nuclear reaction in the reactor by absorbing neutrons by the crawling line. in this case,
By starting pump C and listening to the volume of ↑B and σ injection valve, the boric acid water in the boric acid water tank is injected into the reactor.
（発明か解決しようとり−る問題点）
事故時及び異常な過渡変化時などの非常事態におりる原
子炉の冷却について電動のポンプ等ににる冷却水の注入
を行なわ覆゛重力にＪ、る冷却水の汗ノい原子炉蒸気の
エネルギーを利用した冷却水の注入等を利用して、安全
性を確保する原子炉が考えられている。このような原子
炉においては、この装置のために非常用のディーゼル発
電機等を配置する必要は％い。従来技術によるほう融水
注入装置では専用の大型蓄電池おるいは専用のディーゼ
ル発電機が必要となるといった問題点があった。(Problem to be solved by the invention) To cool down a nuclear reactor in an emergency situation such as an accident or an abnormal transient change, cooling water is injected into an electric pump, etc. to overcome gravity. Nuclear reactors that ensure safety are being considered by utilizing the energy of reactor steam to inject cooling water. In such a nuclear reactor, there is no need to provide an emergency diesel generator or the like for this equipment. The prior art molten water injection device has the problem of requiring a dedicated large storage battery or a dedicated diesel generator.
本発明は上記の問題点を考慮し、電動機駆動のポンプに
よる注入を行なわないことにより、専用のディーゼル発
電機又は大型蓄電池等を必要とせすより信頼性の高いほ
う融水注入装置を得ることになる。The present invention takes the above-mentioned problems into account, and aims to provide a more reliable fused water injection device that does not require a dedicated diesel generator or large storage battery, etc., by eliminating the need for injection using an electric motor-driven pump. Become.
（発明の構成〕
（問題点を解決するための手段）
はう散水タンクより仕切弁を介してタービン駆動ポンプ
に配管を接続し、ざらにタービン駆動ポンプより注入弁
を介して原子炉へ配管を接続する。(Structure of the invention) (Means for solving the problem) Piping is connected from the crawling water tank to the turbine-driven pump through a gate valve, and piping is connected from the turbine-driven pump to the nuclear reactor through an injection valve. Connecting.
一方原子炉の蒸気相部分から加減弁を介して上記タービ
ン駆動ポンプのタービン部分へ配管を接続し、さらにタ
ービンより圧力抑制プールへ配管を接続するほう融水注
入装置である。On the other hand, this is a molten water injection device that connects piping from the steam phase portion of the nuclear reactor to the turbine portion of the turbine-driven pump via a control valve, and further connects piping from the turbine to the pressure suppression pool.
（作 用）
万一制御棒の挿入による原子炉の停止が行なえないよう
な事態か生じた場合、仕切弁及び注入弁を聞（するとと
もに加減弁を１旧プて原子炉蒸気をタービンへ導き、タ
ービン駆動ポンプを作動させることによりほう散水タン
クのほう酸水か原子炉へ流入する。はう素の中′ｉｚｔ
子吸収により原子炉の核反応か停止する。(Function) In the event that a situation arises in which it is not possible to shut down the reactor by inserting control rods, the gate valve and injection valve should be turned on (and the moderation valve should be turned off) to guide the reactor steam to the turbine. , by operating the turbine-driven pump, the boric acid water in the boron water tank flows into the reactor.
The nuclear reaction in the reactor stops due to nuclear absorption.
（実施例） 第１図に本発明の一実施例を示す。(Example) FIG. 1 shows an embodiment of the present invention.
はう散水タンク１から仕切弁２を介してポンプ４に配管
３が接続され、ざらにポンプ４より注入弁５を介して原
子炉７に配管６が接続される。ポンプ４にはタービン１
０と回転軸が接続されている。A piping 3 is connected from the crawling water tank 1 to a pump 4 via a gate valve 2, and a piping 6 is connected from the pump 4 to a nuclear reactor 7 via an injection valve 5. Turbine 1 for pump 4
0 and the rotation axis are connected.
原子炉７の蒸気相部から加減弁８を介し−Ｃタービン１
０へ配管９が接続され、さらにタービン１０から圧力抑
制ブール１２へ配管１１か接続される。タービン１０は
回転数が一定となるよう加減弁８の開度を調整するよう
制御される。-C turbine 1 from the steam phase of the reactor 7 via the control valve 8
A pipe 9 is connected to the turbine 10, and a pipe 11 is also connected from the turbine 10 to the pressure suppression boule 12. The turbine 10 is controlled to adjust the opening degree of the regulating valve 8 so that the rotation speed is constant.
原子炉に４３いて万一制御棒か挿入で゛きないような事
態が発生した場合、仕切弁２、注入弁５、加減弁８を開
く。原子炉７て発生した蒸気はｌＪＤ減弁減音８して配
管９よりタービン１０へ導かれ、タービン１０及びポン
プ８を駆動し、ざらに配管１１を通じて圧力抑制プール
１２へ導かれ凝縮される。一方はう散水タンク１に貯蔵
されているほう酸水は仕切弁２を介して、配管３Ｊ：リ
ボンプ４へ導かれ、ポンプ４で駆動され、注入弁５を介
し、配管６より原子炉７へ注入される。この時タービン
１０及びポンプ４の回転数は加減弁８を制御することに
より一定に保たれるため、注入されるほう酸水の流量は
一定となる。In the unlikely event that a control rod cannot be inserted into a nuclear reactor, the gate valve 2, injection valve 5, and control valve 8 are opened. The steam generated in the nuclear reactor 7 undergoes 1JD valve and noise reduction 8, is guided to a turbine 10 through a pipe 9, drives a turbine 10 and a pump 8, is roughly led to a pressure suppression pool 12 through a pipe 11, and is condensed. On the other hand, the boric acid water stored in the water spray tank 1 is guided through the gate valve 2 to the piping 3J: Ribbon 4, driven by the pump 4, and injected into the reactor 7 from the piping 6 through the injection valve 5. be done. At this time, the rotation speeds of the turbine 10 and the pump 4 are kept constant by controlling the regulating valve 8, so the flow rate of the boric acid water injected is constant.
本実施例では電動機駆動のポンプを使用せずに原子炉へ
のほう散水注入か行なわれるため、電源が喪失した状態
でも非常用のディーゼル発電機や大型蓄電池等の必要が
無く、信頼性の向上、経済性の向上につながる。In this example, water is injected into the reactor without using an electric motor-driven pump, so there is no need for emergency diesel generators or large storage batteries even when power is lost, improving reliability. , leading to improved economic efficiency.
第２図に本発明による他の実施例を示す。FIG. 2 shows another embodiment according to the present invention.
原子炉は下記のような構成の原子炉隔離時冷却装置及び
高圧炉心スプレィ装置を有する。高圧炉心スプレイ装置
は、電動機て駆動されるポンプ１６、復水貯蔵タンク１
３から逆止弁１４を介してポンプ１６に接続される配管
１５、ポンプ１６から注入弁１７を介して原子炉７へ接
続される配管１８により構成される原子炉隔離時冷却装
置は、ポンプ？４及びポンプ２４と回転軸が接続された
タービン２０、高圧炉心スプレィ系の配管１５から分岐
しポンプ２４に接続される配管３ａ、ポンプ２４から注
入弁２５を介して原子炉７に接続される配管２６、原子
炉７の蒸気相部から加減弁２８を介してタービン２０へ
接続される配管２９、及びタービン２０から圧力抑制ブ
ール１２へ接続される配管２１から構成される。The nuclear reactor has a reactor isolation cooling system and a high-pressure core spray system configured as follows. The high-pressure core spray device includes a pump 16 driven by an electric motor, and a condensate storage tank 1.
The reactor isolation cooling system is composed of a pipe 15 connected from the pump 3 to the pump 16 via the check valve 14, and a pipe 18 connected from the pump 16 to the reactor 7 via the injection valve 17. 4 and a turbine 20 to which a rotating shaft is connected to the pump 24, a pipe 3a branched from the high-pressure core spray system pipe 15 and connected to the pump 24, a pipe connected from the pump 24 to the reactor 7 via an injection valve 25. 26, a pipe 29 connected from the steam phase of the reactor 7 to the turbine 20 via the control valve 28, and a pipe 21 connected from the turbine 20 to the pressure suppression boule 12.
本実施例によるほう融水注入装置は、復水貯蔵タンク１
３の水位より高い位置に設置されたほう散水タンク１か
ら仕切弁２２を介して高圧炉心スプレィ装置の配管１５
上の逆止弁１４の下流側で原子炉隔離時冷却装置の配管
３ａの分岐部より上流側の部分に配管２３か接続される
。The molten water injection device according to this embodiment includes a condensate storage tank 1
Piping 15 of the high-pressure core spray system is connected to the water spray tank 1 installed at a higher position than the water level in step 3 via the gate valve 22.
A pipe 23 is connected to a portion downstream of the upper check valve 14 and upstream from a branch of the pipe 3a of the reactor isolation cooling system.
原子炉において万一制御棒か挿入できないような事態が
発生した場合、注入弁２５及び加減弁２８を開き、原子
炉蒸気をタービン２０へ導きポンプ２４を起動し、原子
炉隔離時冷却装置を運転覆る。ざらにほう配水注入装置
の仕切弁２２を聞くことにより、はう酸水タンク１より
ＣＨＩう散水かポンプ２４に導かれ、ポンプ２４−Ｃ駆
動され、原子炉７へ注入される。In the unlikely event that a control rod cannot be inserted in a nuclear reactor, the injection valve 25 and control valve 28 are opened, reactor steam is guided to the turbine 20, the pump 24 is started, and the reactor isolation cooling system is operated. cover By listening to the gate valve 22 of the water distribution injection device, CHI water is guided from the hydrogen atomizer tank 1 to the pump 24, which drives the pump 24-C and injects it into the reactor 7.
これにより原子炉は核反応を停止にする。はう酸水タン
ク１は復水貯蔵タンク１３より高い位置に設置されてい
るため、ますほう散水か原子炉へ注入され、核反応か停
車する。ざらに原子炉の水位が低下している場合には復
水貯蔵タンク水が連続して注入されるため、原子炉の健
全性が確保される。This causes the reactor to stop the nuclear reaction. Since the acid water tank 1 is installed at a higher position than the condensate storage tank 13, water is sprayed or injected into the reactor, and the nuclear reaction is stopped. When the water level in the reactor is dropping, water from the condensate storage tank is continuously injected, ensuring the integrity of the reactor.
Ｊ：た刀−１原了炉隔前時冷却装置か故障した場合には
、高１炉心スプレイ装置のポンプ１６によりほう散水を
原子炉７へ注入することかできる１、はう配水注入装置
は、従来技術のように専用のほう配水注入ポンプを使用
ηることなく、原子炉隔離時冷却装置等のボンｊを利用
し−Ｃはう散水を注入するものであるため、ポンプ・弁
等の動的機器を人１１Ｊに削減−′（き、信頼・目の向
上、保守性の向か
上、経演刊の向上につながる。７また原始炉蒸気により
駆動される原子炉隔離時冷却装置のポンプを使用してい
るため、非常用デイ−セル発電機等の大容量の電源を期
待することなく非常時でのほう配水注入が可能となりよ
り信頼性が向上する。また、高圧炉心スプレィ装置のポ
ンプを利用した注入も可能な構成で必り、さらに信頼性
の高いものとなる。また復水貯蔵タンクの冷水が注入さ
れる前にほう散水か流入するため、冷水の注入で反応度
が上昇するといった危惧を防止できる。J:Tato-1 If the pre-cooling system for the reactor breaks down, water can be injected into the reactor 7 using the pump 16 of the high 1 core spray system1. , instead of using a dedicated water distribution injection pump as in the prior art, the water is injected using a bomb such as a reactor isolation cooling system, so the pumps, valves, etc. Reducing the number of active equipment to 11J people -' (This will lead to improved reliability, improved visibility, improved maintainability, and improved operational efficiency.) 7. Since a pump is used, water can be injected in an emergency without relying on a large-capacity power source such as an emergency day cell generator, improving reliability. The configuration also allows for injection using a pump, making it even more reliable.Also, since cold water from the condensate storage tank is sprinkled or inflowed before being injected, the reactivity increases with the injection of cold water. It is possible to prevent such concerns.
（発明の効果）
信頼性か高く大容量の電源を必要としないほう配水注入
装置を提供出来る。(Effects of the invention) It is possible to provide a water distribution injection device that is highly reliable and does not require a large-capacity power source.
第１図は本発明のほう配水注入装置の系統図、第２図は
他の実施例の系統図、第３図は従来のほう配水注入装置
の系統図である。
１・・・はう酸水タンク、 ２・・・仕切弁、ｉ、１
６．２４・・・ポンプ、 ５，１７．２５・・・注
入弁、７・・・原子炉、 １０．２０・・・
タービン。FIG. 1 is a system diagram of a water distribution injection device of the present invention, FIG. 2 is a system diagram of another embodiment, and FIG. 3 is a system diagram of a conventional distribution water injection device. 1... Acid water tank, 2... Gate valve, i, 1
6.24...Pump, 5,17.25...Injection valve, 7...Nuclear reactor, 10.20...
turbine.
Claims (1)
にポンプ設置することによってほう酸水を原子炉へ注入
できるようにしたほう酸水注入装置において、ポンプを
原子炉蒸気により作動するタービンにより駆動すること
を特徴とするほう酸水注入装置。In a boric acid water injection device that connects piping from the boric acid water tank to the reactor and installs a pump on the piping to inject boric acid water into the reactor, the pump is driven by a turbine operated by reactor steam. A boric acid water injection device characterized by:
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62318654A JPH01161194A (en) | 1987-12-18 | 1987-12-18 | Boric acid injecting device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62318654A JPH01161194A (en) | 1987-12-18 | 1987-12-18 | Boric acid injecting device |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH01161194A true JPH01161194A (en) | 1989-06-23 |
Family
ID=18101545
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP62318654A Pending JPH01161194A (en) | 1987-12-18 | 1987-12-18 | Boric acid injecting device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH01161194A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US20210100133A1 (en) * | 2018-08-01 | 2021-04-01 | Wistron Corp. | Fan system and sound suppression method thereof |
-
1987
- 1987-12-18 JP JP62318654A patent/JPH01161194A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US20210100133A1 (en) * | 2018-08-01 | 2021-04-01 | Wistron Corp. | Fan system and sound suppression method thereof |
| US11558978B2 (en) * | 2018-08-01 | 2023-01-17 | Wistron Corp. | Fan system and sound suppression method thereof |
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