JPH03150498A - Plant operation assisting device for time of sea water leakage in condenser heat transfer pipe - Google Patents
Plant operation assisting device for time of sea water leakage in condenser heat transfer pipeInfo
- Publication number
- JPH03150498A JPH03150498A JP1288904A JP28890489A JPH03150498A JP H03150498 A JPH03150498 A JP H03150498A JP 1288904 A JP1288904 A JP 1288904A JP 28890489 A JP28890489 A JP 28890489A JP H03150498 A JPH03150498 A JP H03150498A
- Authority
- JP
- Japan
- Prior art keywords
- conductivity
- condenser
- plant
- heat transfer
- sea water
- 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
- 239000013535 sea water Substances 0.000 title claims abstract description 39
- 238000012546 transfer Methods 0.000 title claims abstract description 14
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 44
- 230000008929 regeneration Effects 0.000 claims description 11
- 238000011069 regeneration method Methods 0.000 claims description 11
- 238000010612 desalination reaction Methods 0.000 claims 3
- 230000001172 regenerating effect Effects 0.000 abstract description 5
- 238000011033 desalting Methods 0.000 abstract 1
- 238000005342 ion exchange Methods 0.000 description 9
- ZAMOUSCENKQFHK-UHFFFAOYSA-N Chlorine atom Chemical compound [Cl] ZAMOUSCENKQFHK-UHFFFAOYSA-N 0.000 description 7
- 229910052801 chlorine Inorganic materials 0.000 description 7
- 239000000460 chlorine Substances 0.000 description 7
- 238000000746 purification Methods 0.000 description 6
- 239000011347 resin Substances 0.000 description 5
- 229920005989 resin Polymers 0.000 description 5
- 150000002500 ions Chemical class 0.000 description 4
- 239000000498 cooling water Substances 0.000 description 2
- 230000007423 decrease Effects 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 239000002699 waste material Substances 0.000 description 2
- NWUYHJFMYQTDRP-UHFFFAOYSA-N 1,2-bis(ethenyl)benzene;1-ethenyl-2-ethylbenzene;styrene Chemical compound C=CC1=CC=CC=C1.CCC1=CC=CC=C1C=C.C=CC1=CC=CC=C1C=C NWUYHJFMYQTDRP-UHFFFAOYSA-N 0.000 description 1
- -1 CQ- Chemical class 0.000 description 1
- 230000009118 appropriate response Effects 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 238000005336 cracking Methods 0.000 description 1
- 238000005115 demineralization Methods 0.000 description 1
- 230000002328 demineralizing effect Effects 0.000 description 1
- 230000006866 deterioration Effects 0.000 description 1
- 238000003745 diagnosis Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 239000012535 impurity Substances 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 239000003456 ion exchange resin Substances 0.000 description 1
- 229920003303 ion-exchange polymer Polymers 0.000 description 1
- 230000007257 malfunction Effects 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 230000000737 periodic effect Effects 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
- 238000005070 sampling Methods 0.000 description 1
- 239000000126 substance 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
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
【発明の詳細な説明】
〔産業上の利用分野〕
本発明は原子力発電所復水器伝熱管の海水漏えい発生時
におけるプラント運転支援装置に関する。DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to a plant operation support device when seawater leaks from a condenser heat transfer tube of a nuclear power plant.
沸騰水型原子力発電所（ＢＷＲ）の復水器は、蒸気ター
ビンの排蒸気を熱交換により冷却、凝縮した復水にする
設備である。日本の場合、冷却水として海水を使用して
おり、復水器伝熱管内に海水を通水して排蒸気を冷却し
ている。復水は最終的には原子炉へ流入するため、伝熱
管から復水系統内へ海水の漏えいが発生した場合には、
海水中の塩素が原子炉へ混入して炉内構造材の応力腐食
割れの原因となる。従って、これを防止するため、冷却
水として海水を使用するＢＷＲでは、復水器下流に塩素
等の不純物イオンを除去する目的でイオン交換樹脂を装
荷した復水脱塩塔（ＣＤ）を複数基（１１０ＴｊＫＷｅ
クラスて約十基）設置している。しかし、ＣＤ樹脂のイ
オン交換容量を上廻る海水漏えいが発生した場合には、
ＣＤで塩素を除去できなくなり、ＣＤ下流へ塩素が流出
することになるため、イオン交換能力が早く無くなった
塔から、順次、隔離して薬品による再生（イオン交換能
力の回復）作業を行い、再び、通水に戻す必要がある。A condenser in a boiling water nuclear power plant (BWR) is a device that cools exhaust steam from a steam turbine through heat exchange and converts it into condensed water. In Japan, seawater is used as cooling water, and the seawater is passed through the condenser heat transfer tubes to cool the exhaust steam. Condensate ultimately flows into the reactor, so if seawater leaks from the heat transfer tubes into the condensate system,
Chlorine in seawater enters the reactor and causes stress corrosion cracking of structural materials inside the reactor. Therefore, to prevent this, BWRs that use seawater as cooling water install multiple condensate demineralizers (CDs) loaded with ion exchange resin downstream of the condenser to remove impurity ions such as chlorine. (110TjKWe
Approximately 10 units per class) have been installed. However, in the event of seawater leakage that exceeds the ion exchange capacity of CD resin,
Since the CD cannot remove chlorine and the chlorine will flow downstream of the CD, we will sequentially isolate the towers that lost their ion exchange capacity early and regenerate them using chemicals (restore the ion exchange capacity). , it is necessary to return the water to water.
但し、大規模漏えいの場合は、再生によるイオン交換能
力の回復作業が間に合わなくて、炉水へ塩素が混入し炉
水導電率が上昇するケースもあり、プラントを停止する
必要がでてくる。However, in the case of a large-scale leak, the restoration of ion exchange capacity through regeneration may not be done in time, and chlorine may enter the reactor water, increasing the conductivity of the reactor water, making it necessary to shut down the plant.
従来より、海水漏えい発生時には、発電所の当直員が復
水型出［１、ＣＤ出［１、及び、炉水導電率の変化を時
々刻々監視し、海水漏えいを確認して、あらかじめ定め
た導電率の基準値を超える場合には、手動で原子炉をス
クラムすることとしている。Traditionally, when a seawater leak occurs, power plant duty personnel monitor condensate discharge [1], CD discharge [1], and changes in reactor water conductivity from time to time, confirm seawater leakage, and perform predetermined measures. If the conductivity exceeds the standard value, the reactor will be manually scrammed.
このように、海水漏えい発生時の当直員の作業は煩雑で
多忙であり、復水、炉水の導電率」−Ｈの経時変化を予
想し、最適なＣＤ再生のスケジュールを検討する等の時
間的余裕はとりにくい状況となる。In this way, when a seawater leak occurs, the work of the on-call staff is complicated and busy, and they have to spend a lot of time predicting changes over time in the conductivity of condensate and reactor water and considering the optimal CD playback schedule. This creates a situation where it is difficult to have any leeway.
−：３−
上記従来方法は、海水漏えい発生時、発電所の当直員が
復水器出口、ＣＤ出ｒＺＩ、及び、復水導電率の変化を
時々刻々監視しながら、海水漏えいを確認して対応処置
を調整し、あらかじめ定めた導電率の基準値を超える場
合には、手動で原子力４をスクラムすることとしている
。また、復水、炉水の導電率が基準値に達するまでの時
間を予想したり、導電率の上昇を抑制するための最適な
Ｏｒ）再生スケジュールを検討することも必要である。-:3- In the above conventional method, when a seawater leak occurs, the duty staff at the power plant checks the seawater leakage while monitoring the condenser outlet, CD output rZI, and changes in condensate conductivity from time to time. Measures will be adjusted, and if the conductivity exceeds a predetermined standard value, nuclear power 4 will be manually scrammed. It is also necessary to predict the time it will take for the conductivity of condensate and reactor water to reach standard values, and to consider the optimal regeneration schedule for suppressing increases in conductivity.
このように、海水漏えい発生時の当直員の作業は煩雑で
多忙を極める。As described above, the work of the duty staff when a seawater leak occurs is complicated and extremely busy.
本発明の目的は、復水器伝熱管の海水漏えい時の当直員
の煩雑な作業を自動化して軽減することにある。An object of the present invention is to automate and reduce the complicated work of a duty staff when seawater leaks from a condenser heat exchanger tube.
上記目的を達成するために、復水器出口、Ｃ１）出口、
及び、炉水導電率を検出して、基準値登超えた場合には
原子炉緊急停止系にスクラム信号を与える機能を持つと
共に、炉水、ＣＤ出口導電率の経時変化を予想し、さら
に、炉水導電率の任意＝４
の値以上に維持するための最適なＣＤ再生スケジュール
を検討して当直員に対処方法をガイドするプラント診断
機能を持つプラント運転支援装置を設置する。To achieve the above purpose, the condenser outlet, C1) outlet,
It also has the function of detecting the reactor water conductivity and providing a scram signal to the reactor emergency shutdown system if it exceeds the standard value, and predicting changes over time in the reactor water and CD exit conductivity. A plant operation support system will be installed that has a plant diagnosis function that will study the optimal CD playback schedule to maintain the reactor water conductivity above the arbitrary value of 4 and guide shift staff on countermeasures.
ブラント運転支援装置を設置することにより、復水器伝
熱管の海水漏えい時、復水型出１］、ＣＩ’）出口、及
び、炉水の導電率があらかしめ定めた基準値を超える場
合には、自動的に原子炉緊急停止系回路にスクラム信号
を与えることができろため。By installing a blunt operation support system, in the event of seawater leakage from the condenser heat transfer tube, the condensate mold exit 1], CI') outlet, and the conductivity of the reactor water exceed a predetermined standard value. Because it can automatically give a scram signal to the reactor emergency shutdown system circuit.
大規模海水漏えいにより導電率のＬ［が極めて「１（く
、当直員が対応できないような状況でも確実にプラント
スクラムが行える。また、この装置では、スクラム上に
は至らない程度の海水漏えいの場合にも、ＣＤ出ｌ」、
炉水導電率の経時変化予想、及び、最適ＣＤ再生スケジ
ュールを当直員に表示すると共に、ＣＤ再生が間に合わ
ない場合の復水器氷室隔離やプラント通常停止等の処置
を出直員にガイダンス表示することにより、当直員は手
計算による導電率変化予想の時間を短縮でき正確な対応
処置が行える。A plant scram can be performed reliably even in situations where the electrical conductivity is extremely low due to a large-scale seawater leak, and the on-duty personnel cannot respond.In addition, with this device, even if the conductivity is extremely low, the plant scram can be performed even in situations where the on-duty staff cannot respond. In case of CD release,
In addition to displaying predicted changes in reactor water conductivity over time and the optimal CD regeneration schedule to the on-call staff, it also displays guidance to the on-call staff on measures such as isolating the condenser icebox or shutting down the plant in the event that CD regeneration cannot be completed in time. This allows the duty staff to reduce the time it takes to manually calculate changes in conductivity and take accurate countermeasures.
以下、本発明の一実施例を第１図により説明する。蒸気
タービン１の排蒸気は、復水器２内の伝熱管３の内部を
流れる海水により冷却されて復水となる。An embodiment of the present invention will be described below with reference to FIG. Exhaust steam from the steam turbine 1 is cooled by seawater flowing inside the heat exchanger tubes 3 in the condenser 2 and becomes condensed water.
復水はＣＤ４で浄化された後、給水加熱器５で昇温され
、給水ポンプ６で昇圧されて原子炉７へ供給される。原
子炉７には、炉水を浄化するため、原子炉再循環ポンプ
８の人口より分岐し、浄化ポンプ９、再生熱交換器１０
、非再生熱交換器１］、及び、浄化装置１２より構成さ
れる原子炉冷却材浄化系統が設置されている。また、復
水器２出口、ＣＤ４の出１」及び再生熱交換器１０の出
口には、それぞれ、導電率計１３．１−４．１５が設置
されており、復水器伝熱管３で海水漏えいが発生した場
合には、これらの導電率計で、当直員が復水器出口、Ｃ
Ｄ出口、及び、炉水導電率製監視する。After the condensate is purified by the CD 4 , its temperature is raised by the feed water heater 5 , the pressure is increased by the feed water pump 6 , and the water is supplied to the nuclear reactor 7 . In order to purify reactor water, the reactor 7 is equipped with a purification pump 9, a regenerative heat exchanger 10, which branches off from the reactor recirculation pump 8.
, a non-regenerative heat exchanger 1], and a purification device 12. A reactor coolant purification system is installed. In addition, conductivity meters 13.1-4.15 are installed at the condenser 2 outlet, CD4 output 1'', and regenerative heat exchanger 10 outlet, respectively, and the condenser heat exchanger tube 3 In the event of a leak, these conductivity meters will allow duty personnel to check the condenser outlet, C
Monitor D outlet and reactor water conductivity.
本発明では、これら復水器出口導電率計Ｂ、Ｃ。In the present invention, these condenser outlet conductivity meters B and C are used.
Ｄ出口導電率８１１４、及び、炉水導電率計１５の導電
率の信号を、新たに設置する復水器伝熱管海水漏えい時
のプラント運転支援装置１６に入力して、第２図に示す
フローで処理する９、つまり、ＣＤ出［」、あるいは、
炉水導電率があらかじめ設定しである基準値を超える場
合はプラントを停止させるものとし、炉水導ｒＰＬ率の
−１，昇が大きい場合には、プラントスクラム信号を原
子炉緊急停止系へ発信して、自動的にプラントを緊急停
止させる。The D outlet conductivity 8114 and the conductivity signal from the reactor water conductivity meter 15 are input to the newly installed plant operation support device 16 for condenser heat transfer tube seawater leakage, and the flow shown in FIG. 2 is performed. 9, that is, CD output['', or
If the reactor water conductivity exceeds a preset standard value, the plant will be shut down, and if the reactor water conductivity rPL rate -1 or increase is large, a plant scram signal will be sent to the reactor emergency shutdown system. automatically brings the plant to an emergency stop.
基準値を下廻っている場合は、１毎水漏えい量、復水中
塩素濃度、及び、復水器伝熱管漏えい穴径を計算し、さ
らに、それらを画面表示できるようにする。海水中１：
、成分であるＣＱ−、Ｎａ十等のイオンが海水漏えいに
より流入すると、ＣＤ樹脂の貫流イオン交換容量は減少
し、ＣＩ−）出［」、ひいては、炉水の導電率が上昇し
て行くことになる。貫流イオン交換容量はあらかじめプ
ラント起動前の定期点検時にＣ１）樹脂を採取して測定
しておくため、この貫流イオン交換容量測定値を使用し
て、起動後、海水漏えいが発生するまでの通常運転中、
イオン負荷、及び、樹脂劣化による貫流イオン交ＣＤ−
、Ｎａ＋のイオン負荷による貫流イオン交換容量の減少
からＣＤ出口に流出するＣＱ、Ｎａ＋の濃度を計算し、
ＣＤ出口導電率−上昇の経時変化を計算して予想するも
のとする。さらに、炉水に流入するＣＱ″、Ｎａ＋の濃
度から、蒸気中へのキャリオーバー、及び、浄化装置１
２での除去を考慮じて炉水中心電率の経時変化も泪算し
予想するものとする。これらの導電率経時変化の予想結
果は第３図、第４図に示すようなグラフで表示できるも
のとする。If the value is below the standard value, calculate the amount of water leaked per hour, the chlorine concentration in condensate water, and the leakage hole diameter of the condenser heat transfer tube, and display them on the screen. Under seawater 1:
When ions such as CQ-, Na, etc., which are components, flow in due to seawater leakage, the once-through ion exchange capacity of the CD resin decreases, and the conductivity of the reactor water increases. become. Since the once-through ion exchange capacity is measured in advance by sampling C1) resin during periodic inspections before plant startup, this once-through ion exchange capacity measurement value can be used to determine normal operation after startup until seawater leakage occurs. During,
Through-flow ion exchange CD- due to ion loading and resin deterioration
, calculate the concentration of CQ and Na+ flowing out to the CD outlet from the decrease in the through-flow ion exchange capacity due to the ion loading of Na+,
The change in CD exit conductivity-rise over time shall be calculated and predicted. Furthermore, from the concentration of CQ'' and Na+ flowing into the reactor water, there is a carryover into the steam, and the purification device 1
Taking into account the removal in step 2, we will also calculate and predict the change in the reactor water central electric rate over time. The predicted results of these changes in conductivity over time can be displayed in graphs as shown in FIGS. 3 and 4.
次に、炉水導電率を任意の値以下に維持するためのＣＤ
各塔の再生スケジュールを計算する。これは、ＣＤ各塔
出口の導電率経時変化予想から導電率上昇の早い順に６
塔の再生の順番を決め、炉水導電率が任意の値に達した
時点で最初の一塔を再生して導電率を下げ、再度、導電
率が任意の値に達したら次の塔を再生するという様に、
順次、再生して行く最適な再生スケジュールを計算する
再生により発生する廃樹脂は廃棄物処理系に受け入れて
処理されるが、処理容量に制限があるため、この制限も
考慮した再生間隔とするスケジュールにしている。この
再生スケジュール計算結果は、第５図に示すように、表
示できるものとする。Next, CD to maintain the reactor water conductivity below an arbitrary value.
Calculate the regeneration schedule for each tower. This is based on the predicted change in conductivity over time at the outlet of each CD tower, and 6
The order of tower regeneration is determined, and when the reactor water conductivity reaches a desired value, the first tower is regenerated to lower the conductivity, and once the conductivity reaches the desired value, the next tower is regenerated. As if to do,
Calculate the optimal regeneration schedule for sequential regeneration. Waste resin generated through regeneration is accepted into a waste treatment system and processed, but since there is a limit to processing capacity, the regeneration interval is scheduled to take this limit into account. I have to. The reproduction schedule calculation result can be displayed as shown in FIG.
なお、海水漏えい量によってはＣＩ）の再生が間に合わ
ない場合もあるため、復水器氷室の隔離や、プラント通
常停止等の対応処置もガイダンスとして表示できる。Note that, depending on the amount of seawater leakage, it may not be possible to regenerate the CI in time, so countermeasures such as isolating the condenser icebox or shutting down the plant normally can also be displayed as guidance.
以」二の実施例によれば、復水器伝熱管海水漏えい発生
時の発電所当直員の煩雑で多忙な作業を軽減し、適切な
ガイダンス表示をすることにより人為的な誤動作のポテ
ンシャルを低減することができる。According to the second embodiment, the complicated and busy work of power plant duty staff when a condenser heat transfer pipe seawater leak occurs, and the potential for human-induced malfunction is reduced by displaying appropriate guidance. can do.
本発明によれば、海水漏えい時、ＣＤ出１１、あるいは
、炉水導電率が上昇し、あらかじめ設定しである基準値
を超えた場合、スクラム信号として自動的に原子炉緊急
停止系へ発信できる。また、海水漏えい量、復水中塩素
濃度、復水器伝熱管漏えい穴径、Ｃ１）出口、及び、炉
水の導電率予想経時変化、及び、炉水導電率を任意の値
以下に維持するためのＣＤ各塔の再生スケジュールを当
直員に表示できる。さらに、海水漏えい量によっては、
ＣＤの再生が間に合わない場合もあるため、その場合の
復水器氷室隔離やプラント通常停止等の対応処置も当直
員にガイダンスできる。これらにより、）１７ｊ水漏え
い発生時に、当直員の傾雑で多忙な作業を軽減し、当直
員に海水漏えいの規模、緊急性、及び、適切な対応処置
をガイダンスすることから人為的誤操作のポテンシャル
も低減される。According to the present invention, in the event of a seawater leak, if the CD output 11 or the reactor water conductivity increases and exceeds a preset reference value, a scram signal can be automatically transmitted to the reactor emergency shutdown system. . In addition, the amount of seawater leakage, chlorine concentration in condensate, condenser heat exchanger tube leakage hole diameter, C1) exit, and expected changes in reactor water conductivity over time, and to maintain reactor water conductivity below an arbitrary value. The playback schedule for each CD tower can be displayed to the staff on duty. Furthermore, depending on the amount of seawater leakage,
In some cases, the CD may not be played in time, so the on-duty staff can be provided with guidance on countermeasures such as isolating the condenser icebox or shutting down the plant normally. As a result, in the event of a) 17j water leak, the tedious and busy work of the on-duty staff will be reduced, and the on-duty staff will be given guidance on the scale and urgency of the seawater leak, as well as appropriate response measures, thereby reducing the potential for human error. is also reduced.
第１図は本発明の一実施例のＢＷＲプラントに海水漏え
い発生時、プラント運転支援装置を追設した系統図、第
２図はプラント運転支援装置での実行フローチャート、
第３図、第４図および第５図は、それぞれ、上記支援装
置により表示される予想炉水導電率経時変化、ＣＤ出口
予想導電率経時変化、及び、ＣＤ再生予定スケジュール
の画面表示例図である。
１・・・蒸気タービン、２・復水器、３ ・復水器伝熱
管、４・・・復水脱塩塔（ＣＤ）、５・給水加熱器、６
・・・給水ポンプ、７・・原子炉、８・・・原子炉再循
環ポンプ、９・浄化ポンプ、１０ 再生熱交換器、１１
・・・非再生熱交換器、１２ 浄化装置、１３ ・−１
，１Fig. 1 is a system diagram of a BWR plant according to an embodiment of the present invention in which a plant operation support device is added when a seawater leak occurs, and Fig. 2 is an execution flowchart of the plant operation support device.
Figures 3, 4, and 5 are screen display examples of the predicted reactor water conductivity change over time, CD exit expected conductivity change over time, and CD playback schedule displayed by the support device, respectively. be. 1... Steam turbine, 2. Condenser, 3. Condenser heat transfer tube, 4. Condensate demineralization tower (CD), 5. Feed water heater, 6
...Water pump, 7.. Nuclear reactor, 8.. Reactor recirculation pump, 9. Purification pump, 10. Regenerative heat exchanger, 11.
...Non-regenerative heat exchanger, 12 Purification device, 13 ・-1
,1
Claims (1)
復水及び炉水の導電率の上昇を検出し、プラント運転の
継続、あるいは、スクラムを自動的に判断すると共に、
必要な場合は、プラントを自動的にスクラムさせること
を特徴とする復水器伝熱管海水漏えい時のプラント運転
支援装置。 ２、請求項１において、海水漏えい後の炉水及び復水脱
塩装置の出口の導電率変化を予想し、それを発電所当直
員にガイダンス表示する復水器伝熱管海水漏えい時のプ
ラント運転支援装置。 ３、請求項１において、炉水、あるいは、復水脱塩装置
出口導電率を任意の値以下に維持するための復水脱塩装
置再生スケジュールを検討し、それを発電所当直員にガ
イダンス表示する復水器伝熱管海水漏えい時のプラント
運転支援装置。[Claims] 1. When seawater leaks from a heat exchanger tube of a condenser at a nuclear power plant,
Detects increases in conductivity of condensate and reactor water and automatically determines whether to continue plant operation or scram.
A plant operation support system in the event of seawater leakage from a condenser heat transfer tube, which automatically scrams the plant if necessary. 2. In claim 1, the plant operation at the time of a seawater leak in a condenser heat transfer tube predicts changes in the conductivity of the reactor water and the outlet of the condensate desalination equipment after a seawater leak and displays it as guidance to power plant duty personnel. Support equipment. 3. In claim 1, consider a condensate desalination equipment regeneration schedule to maintain reactor water or condensate desalination equipment outlet conductivity below an arbitrary value, and display it as guidance to power plant duty staff. A plant operation support system in the event of a seawater leak from a condenser heat transfer tube.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1288904A JPH03150498A (en) | 1989-11-08 | 1989-11-08 | Plant operation assisting device for time of sea water leakage in condenser heat transfer pipe |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1288904A JPH03150498A (en) | 1989-11-08 | 1989-11-08 | Plant operation assisting device for time of sea water leakage in condenser heat transfer pipe |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH03150498A true JPH03150498A (en) | 1991-06-26 |
Family
ID=17736293
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1288904A Pending JPH03150498A (en) | 1989-11-08 | 1989-11-08 | Plant operation assisting device for time of sea water leakage in condenser heat transfer pipe |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH03150498A (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO1995016900A1 (en) * | 1993-12-14 | 1995-06-22 | Somerset Technical Laboratories Limited | Leakage detection |
| GB2284674B (en) * | 1993-10-02 | 1996-09-25 | Somerset Technical Lab Ltd | Leakage testing |
| US5739420A (en) * | 1996-09-18 | 1998-04-14 | Peterson; Roger | Ground water infiltration detection system |
| US5872308A (en) * | 1993-10-02 | 1999-02-16 | Somerset Technical Laboratories Limited | Method of testing a plate heat exchanger for leakage |
-
1989
- 1989-11-08 JP JP1288904A patent/JPH03150498A/en active Pending
Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB2284674B (en) * | 1993-10-02 | 1996-09-25 | Somerset Technical Lab Ltd | Leakage testing |
| US5872308A (en) * | 1993-10-02 | 1999-02-16 | Somerset Technical Laboratories Limited | Method of testing a plate heat exchanger for leakage |
| WO1995016900A1 (en) * | 1993-12-14 | 1995-06-22 | Somerset Technical Laboratories Limited | Leakage detection |
| GB2291192A (en) * | 1993-12-14 | 1996-01-17 | Somerset Technical Lab Ltd | Leakage detection |
| GB2291192B (en) * | 1993-12-14 | 1996-06-12 | Somerset Technical Lab Ltd | Leakage detection |
| US6044692A (en) * | 1993-12-14 | 2000-04-04 | Somerset Technical Laboratories Limited | Ultrasonic method of testing a plate heat exchanger for leakage |
| US6062068A (en) * | 1993-12-14 | 2000-05-16 | Somerset Technical Laboratories Ltd. | Leakage testing method for a plate heat exchanger |
| EP1003024A1 (en) * | 1993-12-14 | 2000-05-24 | Somerset Technical Laboratories Limited | Leakage detection |
| US5739420A (en) * | 1996-09-18 | 1998-04-14 | Peterson; Roger | Ground water infiltration detection system |
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