JPS62280689A - Nuclear reactor coolant purifying system - Google Patents
Nuclear reactor coolant purifying systemInfo
- Publication number
- JPS62280689A JPS62280689A JP61124326A JP12432686A JPS62280689A JP S62280689 A JPS62280689 A JP S62280689A JP 61124326 A JP61124326 A JP 61124326A JP 12432686 A JP12432686 A JP 12432686A JP S62280689 A JPS62280689 A JP S62280689A
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- boric acid
- filter
- reactor coolant
- purification system
- 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
- 239000002826 coolant Substances 0.000 title claims description 18
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 42
- 239000004327 boric acid Substances 0.000 claims description 27
- KGBXLFKZBHKPEV-UHFFFAOYSA-N boric acid Chemical compound OB(O)O KGBXLFKZBHKPEV-UHFFFAOYSA-N 0.000 claims description 26
- 238000000746 purification Methods 0.000 claims description 15
- 238000002347 injection Methods 0.000 claims description 9
- 239000007924 injection Substances 0.000 claims description 9
- 238000011144 upstream manufacturing Methods 0.000 claims description 4
- 229910011255 B2O3 Inorganic materials 0.000 claims 1
- JKWMSGQKBLHBQQ-UHFFFAOYSA-N diboron trioxide Chemical compound O=BOB=O JKWMSGQKBLHBQQ-UHFFFAOYSA-N 0.000 claims 1
- 239000012530 fluid Substances 0.000 claims 1
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 7
- 229910052796 boron Inorganic materials 0.000 description 7
- 230000001172 regenerating effect Effects 0.000 description 4
- 230000000694 effects Effects 0.000 description 3
- 238000010438 heat treatment Methods 0.000 description 3
- 239000007921 spray Substances 0.000 description 3
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 2
- 229910021538 borax Inorganic materials 0.000 description 2
- 239000003758 nuclear fuel Substances 0.000 description 2
- VPOLVWCUBVJURT-UHFFFAOYSA-N pentadecasodium;pentaborate Chemical compound [Na+].[Na+].[Na+].[Na+].[Na+].[Na+].[Na+].[Na+].[Na+].[Na+].[Na+].[Na+].[Na+].[Na+].[Na+].[O-]B([O-])[O-].[O-]B([O-])[O-].[O-]B([O-])[O-].[O-]B([O-])[O-].[O-]B([O-])[O-] VPOLVWCUBVJURT-UHFFFAOYSA-N 0.000 description 2
- 235000010339 sodium tetraborate Nutrition 0.000 description 2
- 239000000243 solution Substances 0.000 description 2
- BSVBQGMMJUBVOD-UHFFFAOYSA-N trisodium borate Chemical compound [Na+].[Na+].[Na+].[O-]B([O-])[O-] BSVBQGMMJUBVOD-UHFFFAOYSA-N 0.000 description 2
- 230000002159 abnormal effect Effects 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 238000005253 cladding Methods 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 239000000498 cooling water Substances 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 229910052742 iron Inorganic materials 0.000 description 1
- 238000002955 isolation Methods 0.000 description 1
- 238000001556 precipitation Methods 0.000 description 1
- 238000011403 purification operation Methods 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 230000003134 recirculating effect Effects 0.000 description 1
- 239000011347 resin Substances 0.000 description 1
- 229920005989 resin Polymers 0.000 description 1
- 230000035939 shock Effects 0.000 description 1
- 238000005507 spraying Methods 0.000 description 1
- 230000007704 transition Effects 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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
〔産業上の利用分野〕
本発明は原子炉の水質向上のための原子炉冷却材浄化シ
ステムに係り、特に原子炉冷温停止機能としてのほう酸
水注入装置を設けた原子炉冷却材浄化システムに関する
。[Detailed Description of the Invention] [Field of Industrial Application] The present invention relates to a reactor coolant purification system for improving the water quality of a nuclear reactor, and particularly relates to a nuclear reactor coolant purification system for improving the water quality of a nuclear reactor, and particularly for a nuclear reactor equipped with a boric acid water injection device as a cold shutdown function of a nuclear reactor. Relating to a reactor coolant purification system.
沸騰水型原子炉には特開昭54−112489号公報記
載のように原子炉停止装置としてのほう酸木注入プレイ
系ポンプによりほう酸水注入を行なうようにしたもので
ある。この高圧炉心スプレィ系ポンプは、炉水の喪失事
故時などに炉心に冷却水をスプレィして炉水の水位を回
復させるためものもであり、一般に定格が約350rd
/hと大容量のものである。Boric acid water is injected into a boiling water reactor using a boric acid injection play system pump as a reactor shutdown device, as described in Japanese Patent Application Laid-Open No. 112489/1983. This high-pressure core spray pump is used to restore the water level of the reactor core by spraying cooling water in the event of a loss of reactor water accident, and generally has a rating of approximately 350rd.
It has a large capacity of /h.
しかしながらほう酸べを収納するタンクは約200−と
小容量であり、この量を約1時間で注入するのが一般的
であるため、前記高圧炉心スプレイ系ポンプでは容量が
大きすぎて適切でないという問題があった。その理由は
原子炉内の水位が一定の水位まで上昇すると、高圧炉心
スプレィ系注入弁が閉じるため、原子炉の緊急停止時に
必要なほう酸濃度に達しない場合があるためである。However, the tank that stores boric acid has a small capacity of about 200 kg, and it is common to inject this amount in about 1 hour, so the above-mentioned high-pressure core spray system pump has a problem that the capacity is too large and is not suitable. was there. The reason for this is that when the water level inside the reactor rises to a certain level, the high-pressure core spray system injection valve closes, which may not reach the boric acid concentration required for an emergency shutdown of the reactor.
本発明は上記事情に鑑みてなされたものであり、原子炉
の緊急停止時に適切な時間内に原子炉内のほう素の濃度
を必要な濃度まで上昇させることのできる原子炉冷却材
浄化システムを提供することを目的とする。The present invention has been made in view of the above circumstances, and provides a reactor coolant purification system that can increase the concentration of boron in the reactor to a required concentration within an appropriate time during an emergency shutdown of a nuclear reactor. The purpose is to provide.
C問題点を解決するための手段〕
本発明は上記の目的を達成するために、原子炉に接続さ
れ閉ループを形成する配管中に設けられたフィルタの上
流側に、前記配管と並列にほう酸水注入装置を設けたも
のである。Means for Solving Problem C] In order to achieve the above object, the present invention provides a solution of boric acid solution in parallel with the piping, upstream of the filter provided in the piping connected to the nuclear reactor and forming a closed loop. It is equipped with an injection device.
上記の構成によると、原子炉冷却材浄化系は高圧低流量
ポンプを有する常用運転系であり、yK子炉の炉水を浄
化するための閉ループを形成しているので、この原子炉
冷却材浄化系にほう酸水注入装置を設けても原子炉内の
炉水の水位は一定に保たれるため、原子炉内のほう青濃
度は容易に制御できる。According to the above configuration, the reactor coolant purification system is a normally operating system with a high-pressure, low-flow pump, and forms a closed loop for purifying the reactor water of the yK sub-reactor. Even if the system is equipped with a boric acid water injection device, the water level in the reactor is kept constant, so the concentration of boron in the reactor can be easily controlled.
以下、本発明に係る原子炉冷却材浄化システムの一実施
例を図面を参照して説明する。EMBODIMENT OF THE INVENTION Hereinafter, one embodiment of the nuclear reactor coolant purification system according to the present invention will be described with reference to the drawings.
第1図に本発明の一実施例を示す0図において。FIG. 1 shows an embodiment of the present invention.
原子炉1にはこの原子炉1内の炉水を再循環させるため
冷却材再循環ポンプ2が設けられており、このポンプ2
の上流側には炉水を抽出するための閉ループ状の配管3
の一端が接続されている。この配管3には順次再生熱交
換器4.非再生熱交換器5.2台の原子炉冷却材浄化系
ポンプ6、フィルタ7が設けられており、この配管3の
他端は再び前記再生熱交換器4を通って原子炉1に接続
されている。前記フィルタ7は樹脂などで形成されてお
り放射性物質が付着した鉄クラツドなどを吸収する作用
をなし、前後に隔離弁8が設けられている。このフィル
タ7の上流側の配管3には第1のバイパス9が設けられ
ており、バイパス9と並列の部分の配管3にはほう酸水
タンクバイパス弁10が設けられている。このバイパス
9には前後に出入口弁11が取付けられたほう酸水タン
ク12が設けらている。そして出入口弁11の外側間に
接続されてほう酸水タンク12内を貫通する小口径の加
温用配管13が設けられている。またフィルタフに並列
にs+s*#e;?辷嗜の外側間が第2のバイパス14
によって接続されており、この第2のバイパス14には
フィルタバイパス弁15が設けられている。また配管3
のフィルタ7に対して下流側には、復水器ブローダウン
弁16を介して復水器17が接続されている。18は核
燃料。The reactor 1 is equipped with a coolant recirculation pump 2 for recirculating reactor water within the reactor 1.
Closed loop piping 3 for extracting reactor water is installed on the upstream side of
is connected at one end. This piping 3 is connected to a regenerative heat exchanger 4. A non-regenerative heat exchanger 5. Two reactor coolant purification system pumps 6 and a filter 7 are provided, and the other end of this pipe 3 is connected to the reactor 1 through the regenerative heat exchanger 4 again. ing. The filter 7 is made of resin or the like and has the function of absorbing iron cladding to which radioactive substances have adhered, and isolating valves 8 are provided at the front and rear of the filter 7. A first bypass 9 is provided in the piping 3 on the upstream side of the filter 7, and a boric acid water tank bypass valve 10 is provided in a portion of the piping 3 parallel to the bypass 9. This bypass 9 is provided with a boric acid water tank 12 to which inlet and outlet valves 11 are attached at the front and rear. A small diameter heating pipe 13 is provided which is connected between the outer sides of the inlet and outlet valves 11 and penetrates through the boric acid water tank 12. Also, in parallel with the filter s+s*#e;? The second bypass 14 is located between the outside of the slippery
This second bypass 14 is connected by a filter bypass valve 15 . Also, piping 3
A condenser 17 is connected to the downstream side of the filter 7 via a condenser blowdown valve 16 . 18 is nuclear fuel.
19は制御棒である。19 is a control rod.
次に本、実施例の作用を説明する。原子炉燃料の核分裂
反応は炉水内のほう素が11000PPに達すると抑制
され、原子炉を冷温停止状態に移行できる。Next, the operation of this embodiment will be explained. The nuclear fission reaction in the reactor fuel is suppressed when the boron in the reactor water reaches 11,000 PP, allowing the reactor to enter a cold shutdown state.
このために現在の原子力発電所においては、原子炉を冷
温停止させるために炉内のほう素の濃度を毎分約8 P
PMの割合で増加できる専用ポンプを設置している0本
実施例のポンプ6はこの条件以上の性能を持つ高圧低流
量ポンプである。またポンプ6は並列に2台設置し、1
台が故障しても注入に支障がないようになっている。そ
してこのポンプ6を使用することにより従来に比べ約1
/4の時間内に必要なほう酸ナトリウムを原子炉1内に
注入することができる。For this reason, in current nuclear power plants, the concentration of boron in the reactor is reduced to about 8 P per minute in order to bring the reactor to cold shutdown.
The pump 6 of this embodiment, which is equipped with a dedicated pump that can increase the rate of PM, is a high-pressure, low-flow pump that has performance exceeding this condition. In addition, two pumps 6 are installed in parallel, and one
Even if the stand breaks down, there will be no problem with injection. And by using this pump 6, compared to the conventional one, approximately 1
The required sodium borate can be injected into the reactor 1 within a time of /4.
次に通常の原子炉冷却材浄化運転から原子炉冷温停止運
転への移行について説明する。Next, the transition from normal reactor coolant purification operation to reactor cold shutdown operation will be explained.
原子炉通常運転時にはほう酸水タンク12は出入口弁1
1により隔離されており、バイパス弁10が開いていて
、熱交換器4,5で約280℃から約60℃まで冷却さ
れた炉水がポンプ6によって1台当り約60留/秒の流
速で圧送され、フィルタ7で浄化された後に原子炉1に
戻される。During normal reactor operation, the boric acid water tank 12 is closed to the inlet/outlet valve 1.
1, the bypass valve 10 is open, and the reactor water cooled from about 280°C to about 60°C by the heat exchangers 4 and 5 is pumped by the pump 6 at a flow rate of about 60 ref/sec per unit. It is pumped, purified by a filter 7, and then returned to the reactor 1.
このときに万一ほう酸水タンク12から五ほう酸トナト
リウムが系統内に漏洩しても、タンク12の下流側に設
けられたフィルタ7で除去されるため、炉水中のほう青
濃度が上昇して原子炉出力に影響を及ぼすことはない。Even if tosodium pentaborate leaks into the system from the boric acid water tank 12 at this time, it will be removed by the filter 7 installed downstream of the tank 12, so the concentration of sodium pentaborate in the reactor water will increase. It has no effect on reactor output.
なおこのときバイパス弁15は閉じている。Note that the bypass valve 15 is closed at this time.
原子炉冷温停止運転に際しては、フィルタ7のバイパス
弁15を開き、隔離弁8を閉じて五ほう酸ナトリウムが
フィルタ7内に流入することを防止する。次にほう酸水
タンク出入口弁11を開きバイパス弁1oを閉じて原子
炉1内へほう酸水を注入する。During reactor cold shutdown operation, the bypass valve 15 of the filter 7 is opened and the isolation valve 8 is closed to prevent sodium pentaborate from flowing into the filter 7. Next, the boric acid water tank inlet/outlet valve 11 is opened, the bypass valve 1o is closed, and boric acid water is injected into the reactor 1.
本実施例ではほう酸水を注入するときに使用する原子炉
冷却材浄化系が、原子炉から抽出した炉水を原子炉へ戻
す閉ループであるため、運転モードを切り換えてほう酸
水を注入する際にも原子炉水位は変化せず、水位が安定
した状態で原子炉内のほう素濃度を従来の約174の時
間で必要濃度まで上昇させることができる。またほう酸
水タンク12内のほう酸水は加温ライン13によって通
常運転巾約60℃の炉水に接しているため、従来必要で
あったほう酸ナトリウム析出防止用ヒータが不要となる
。またほう酸水注入のための専用ポンプも不要となる。In this example, the reactor coolant purification system used when injecting boric acid water is a closed loop that returns reactor water extracted from the reactor to the reactor. However, the reactor water level does not change, and while the water level remains stable, the boron concentration within the reactor can be raised to the required concentration in about 174 hours compared to conventional methods. Further, since the boric acid water in the boric acid water tank 12 is in contact with reactor water having a normal operating width of about 60° C. through the heating line 13, a heater for preventing sodium borate precipitation, which was conventionally necessary, is no longer necessary. Also, a dedicated pump for injecting boric acid water is not required.
さらに漏洩したほう酸水をフィルタ7で吸着処理できる
ため炉水のほう素濃度に影響はない。また常用運転ポン
プをほう酸水注人に使用するため、非常用機器に対して
行なわれるサーベランステストが不要となり、動的機器
としてのポンプの信頼性が向上する。またほう酸水タン
ク12を低温部(60℃以下)に設置できるため、タン
ク内の圧力の異常昇圧を防止できる。Furthermore, since the leaked boric acid water can be adsorbed and treated by the filter 7, the boron concentration in the reactor water is not affected. Furthermore, since the normally operating pump is used for injecting boric acid water, there is no need for surveillance tests performed on emergency equipment, improving the reliability of the pump as a dynamic equipment. Furthermore, since the boric acid water tank 12 can be installed in a low temperature area (60° C. or lower), abnormal pressure increases in the tank can be prevented.
さらに原子炉1内に注入されるほう酸水は再生熱交換器
4により200℃位まで昇温されているため、ほう酸水
注入により従来生じていた原子炉圧力容器ノズル部の熱
衝撃は防止できる。なお加温ライン13はなくても出入
口弁11が常に約60℃の炉水に接しているのでなくて
もよい。Further, since the temperature of the boric acid water injected into the reactor 1 is raised to about 200° C. by the regenerative heat exchanger 4, the thermal shock of the nozzle portion of the reactor pressure vessel, which conventionally occurs due to the injection of boric acid water, can be prevented. Note that even if the heating line 13 is not provided, the inlet/outlet valve 11 is always in contact with reactor water at about 60° C., so it is not necessary.
上述したように本発明によれば、ほう酸水タンクを原子
炉冷却材浄化系に設けたので1M子炉緊急停止時に適切
な時間内に原子炉内のほう素濃度を必要な濃度まで上昇
させることができる。As described above, according to the present invention, since the boric acid water tank is provided in the reactor coolant purification system, it is possible to raise the boron concentration in the reactor to the required concentration within an appropriate time during an emergency shutdown of the 1M sub-reactor. Can be done.
第1図は本発明の原子炉冷却材浄化システムの一実施例
を示す構成図である。
1・・・原子炉、2・・・ポンプ、3・・・配管、4,
5・・・熱交換器、7・・・フィルタ、10・・・ほう
酸水タンクバイパス弁、12・・−ほう酸水タンク、1
4・・・バイパス、15・・・フィルタバイパス弁。FIG. 1 is a block diagram showing an embodiment of the reactor coolant purification system of the present invention. 1... Nuclear reactor, 2... Pump, 3... Piping, 4,
5... Heat exchanger, 7... Filter, 10... Boric acid water tank bypass valve, 12... - Boric acid water tank, 1
4... Bypass, 15... Filter bypass valve.
Claims (1)
ンプと、フィルタと、熱交換器を設けてなる原子炉冷却
材浄化システムにおいて、前記フィルタの上流側に前記
配管と並列にほう酸化注入装置を設けたことを特徴とす
る原子炉冷却材浄化システム。 2、ほう酸水注入装置と配管とはバイパス弁により水路
切替えを可能としたことを特徴とする特許請求の範囲第
1項記載の原子炉冷却材浄化システム。 3、配管中に設けられたフィルタは、このフィルタに並
列に設けられたバイパス弁を有するバイパスにより、配
管中を流れる流体のフィルタ通過不通過の切替え可能と
したことを特徴とする特許請求の範囲第1項記載の原子
炉冷却材浄化システム。[Claims] 1. In a reactor coolant purification system that includes a pump, a filter, and a heat exchanger in piping that is connected to a nuclear reactor and forms a closed loop, the piping is provided upstream of the filter. A reactor coolant purification system characterized by having a boric oxide injection device installed in parallel with the reactor coolant purification system. 2. The reactor coolant purification system according to claim 1, wherein the boric acid water injection device and the piping can be switched by a bypass valve. 3. Claims characterized in that the filter provided in the pipe is capable of switching between passing and not passing the fluid flowing through the pipe by a bypass having a bypass valve provided in parallel to the filter. The reactor coolant purification system according to item 1.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP61124326A JPS62280689A (en) | 1986-05-29 | 1986-05-29 | Nuclear reactor coolant purifying system |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP61124326A JPS62280689A (en) | 1986-05-29 | 1986-05-29 | Nuclear reactor coolant purifying system |
Publications (1)
Publication Number | Publication Date |
---|---|
JPS62280689A true JPS62280689A (en) | 1987-12-05 |
Family
ID=14882569
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP61124326A Pending JPS62280689A (en) | 1986-05-29 | 1986-05-29 | Nuclear reactor coolant purifying system |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS62280689A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN112331370A (en) * | 2020-11-17 | 2021-02-05 | 深圳中广核工程设计有限公司 | Emergency boronizing system for nuclear power station |
Citations (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS5733390A (en) * | 1980-08-08 | 1982-02-23 | Hitachi Ltd | Liquid neutron absorber injecting system |
-
1986
- 1986-05-29 JP JP61124326A patent/JPS62280689A/en active Pending
Patent Citations (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS5733390A (en) * | 1980-08-08 | 1982-02-23 | Hitachi Ltd | Liquid neutron absorber injecting system |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN112331370A (en) * | 2020-11-17 | 2021-02-05 | 深圳中广核工程设计有限公司 | Emergency boronizing system for nuclear power station |
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JPH0454915B2 (en) | ||
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