JPH049277B2 - - Google Patents
Info
- Publication number
- JPH049277B2 JPH049277B2 JP58105688A JP10568883A JPH049277B2 JP H049277 B2 JPH049277 B2 JP H049277B2 JP 58105688 A JP58105688 A JP 58105688A JP 10568883 A JP10568883 A JP 10568883A JP H049277 B2 JPH049277 B2 JP H049277B2
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- vacuum
- vessel
- water
- main condenser
- 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 - Lifetime
Links
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 35
- 239000007789 gas Substances 0.000 claims description 22
- 238000000034 method Methods 0.000 claims description 14
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 claims description 13
- 229910052760 oxygen Inorganic materials 0.000 claims description 13
- 239000001301 oxygen Substances 0.000 claims description 13
- 230000001965 increasing effect Effects 0.000 claims description 8
- 239000007921 spray Substances 0.000 claims description 7
- 239000002826 coolant Substances 0.000 claims description 4
- 238000003756 stirring Methods 0.000 claims description 4
- 238000009835 boiling Methods 0.000 claims description 3
- 238000000746 purification Methods 0.000 claims description 2
- 239000008213 purified water Substances 0.000 claims description 2
- 238000007872 degassing Methods 0.000 description 10
- 230000000694 effects Effects 0.000 description 9
- 238000010586 diagram Methods 0.000 description 7
- 238000002955 isolation Methods 0.000 description 7
- 238000009849 vacuum degassing Methods 0.000 description 6
- 238000011017 operating method Methods 0.000 description 5
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 4
- 238000007789 sealing Methods 0.000 description 3
- 229910000963 austenitic stainless steel Inorganic materials 0.000 description 2
- 230000007797 corrosion Effects 0.000 description 2
- 238000005260 corrosion Methods 0.000 description 2
- 238000005336 cracking Methods 0.000 description 2
- 239000000446 fuel Substances 0.000 description 2
- 239000011261 inert gas Substances 0.000 description 2
- 238000012806 monitoring device Methods 0.000 description 2
- 238000010926 purge Methods 0.000 description 2
- 230000001172 regenerating effect Effects 0.000 description 2
- 238000001179 sorption measurement Methods 0.000 description 2
- 238000004891 communication Methods 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 230000002708 enhancing effect Effects 0.000 description 1
- 239000010858 gaseous radioactive waste Substances 0.000 description 1
- 210000004907 gland Anatomy 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 150000002926 oxygen Chemical class 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 230000003449 preventive effect Effects 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 238000005070 sampling Methods 0.000 description 1
- 238000004904 shortening Methods 0.000 description 1
- 238000005507 spraying 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
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Treatment Of Water By Oxidation Or Reduction (AREA)
Description
【発明の詳細な説明】
〔発明の利用分野〕
本発明は、沸騰水型原子力発電プラントの運転
方法に係り、特に、原子炉一次系のオーステナイ
ト系ステンレス鋼の応力腐食割れを防止するに好
適な原子炉起動時の炉水中溶存酸素脱気方法に関
する。[Detailed Description of the Invention] [Field of Application of the Invention] The present invention relates to a method of operating a boiling water nuclear power plant, and in particular, a method suitable for preventing stress corrosion cracking of austenitic stainless steel in the primary system of a nuclear reactor. This article relates to a method for degassing dissolved oxygen in reactor water during reactor startup.
従来の原子炉起動時の脱気運転方法に関して
は、原子炉圧力容器内の炉水中の溶存酸素濃度を
200ppb以下程度に脱気してから、原子炉出力を
上昇する運転方法が知られている。ひとつは、原
子炉容器内を不活性ガスを用いて、脱気する方法
とタービンの主復水器の真空度を用いて、原子炉
を真空脱気する方法がある。前者は、不活性ガス
を充填する設備と抽出する設備が必要でありコス
ト高となるという欠点があるため、一部のプラン
トを除いて、あまり利用されていない。一方後者
は、既存設備の真空装置を利用することによつて
容易に実施できるため、運転に供されつつある。
しかし、主復水器の真空度を利用した運転法のた
め、原子炉起動する時間が、長くなり、プラント
の設備稼動率を小さくし、発電量の損失となるこ
とを認めて、運転せざるを得ないという欠点があ
つた。従来技術のうち、真空脱気法の運転関連設
備と運転法を第1図で説明する。原子炉容器1内
の炉水24の溶存酸素を脱気する場合、まず、所
内ボイラ(H・B)で発生した蒸気を弁17を弁
して、配管18を通して、高圧タービン7および
低圧タービン8のグランドシールを行う。と同時
に、主復水器9の真空と上昇するため、排ガス配
管11より、主復水器内の空気を真空ポンプ12
により、主排気筒13に放出する。真空ポンプの
真空能力に達すると、さらに高真空とするため
に、起動用エゼクター14を起動し、並列運転と
する。その後、真空ポンプ12を停止し、起動用
エゼクターのみによる真空上昇および真空維持を
行う。なお、この場合、排気は、活性炭吸着塔を
介して、主排気筒へ排出することができる。この
ような状態になつてから、原子炉容器を密閉にし
たのち、主蒸気ドレン弁隔離弁21および22を
開とし、MSドレン弁23を開とすることによ
り、主復水器9と原子炉容器1を連通させ、主復
水器の高真空を用いて、原子炉容器気相部25を
負圧にして、炉水24の脱気を達成する。しかる
後に、主蒸気隔離弁3,4および5弁6,10を
開として原子炉を起動し、炉水温度上昇を開始す
る。
Regarding the conventional degassing operation method at reactor startup, the dissolved oxygen concentration in the reactor water in the reactor pressure vessel is
An operating method is known in which the reactor output is increased after degassing to about 200 ppb or less. One method is to evacuate the inside of the reactor vessel using an inert gas, and the other is to evacuate the reactor under vacuum using the vacuum level of the main condenser of the turbine. The former method requires equipment for filling inert gas and equipment for extracting it, resulting in high costs, so it is not used much except in some plants. On the other hand, the latter method is being put into operation because it can be easily implemented by using existing vacuum equipment.
However, since the operating method utilizes the vacuum level of the main condenser, the reactor startup time will be longer, reducing the plant's equipment operating rate and causing a loss in power generation, so operation has to be continued. The drawback was that it did not provide any benefits. Among the conventional techniques, the operation-related equipment and operation method of the vacuum degassing method will be explained with reference to FIG. When degassing the dissolved oxygen in the reactor water 24 in the reactor vessel 1, first, the steam generated in the in-house boiler (H・B) is passed through the valve 17 through the pipe 18 to the high-pressure turbine 7 and the low-pressure turbine 8. Perform a ground seal. At the same time, in order to increase the vacuum in the main condenser 9, the air in the main condenser is pumped through the exhaust gas pipe 11 to the vacuum pump 12.
As a result, it is released into the main exhaust stack 13. When the vacuum capacity of the vacuum pump is reached, the starting ejector 14 is started to create a higher vacuum and parallel operation is performed. Thereafter, the vacuum pump 12 is stopped, and the vacuum is raised and maintained only by the starting ejector. In this case, the exhaust gas can be discharged to the main exhaust stack via the activated carbon adsorption tower. In this state, after sealing the reactor vessel, the main steam drain valve isolation valves 21 and 22 are opened, and the MS drain valve 23 is opened, thereby disconnecting the main condenser 9 and the reactor. The vessel 1 is brought into communication and the high vacuum of the main condenser is used to create a negative pressure in the reactor vessel gas phase section 25, thereby achieving degassing of the reactor water 24. Thereafter, the main steam isolation valves 3, 4 and 5 valves 6, 10 are opened to start the reactor and begin to raise the reactor water temperature.
なお、起動する場合は、炉水24の温度均一化
および、脱気効果を高めるために、再循環ポンプ
20を運転して、炉水を撹拌させている。 In addition, when starting up, in order to equalize the temperature of the reactor water 24 and enhance the deaeration effect, the recirculation pump 20 is operated to stir the reactor water.
なお、原子炉で蒸気が発生しはじめると、エバ
ポレタ19により、発生した蒸気を配管18に送
り、タービンのグランドシールを行う。この段階
になると、弁17は閉止する。 Note that when steam starts to be generated in the nuclear reactor, the evaporator 19 sends the generated steam to the pipe 18 to perform ground sealing of the turbine. At this stage, the valve 17 is closed.
以上の運転操作の第2図で示す。復水器真空ポ
ンプ起動と同時に、曲線Aのラインにそつて真空
上昇を開始する。真空ポンプを停止後、MSドレ
ン弁を開として、曲線Bにそつて、原子炉容器内
の真空を上昇する。原子炉容器内の真空を約3時
間維持することにより、炉水の溶存酸素を脱気す
る。炉水溶存酸素濃度が200ppb以下になるとモ
ードスイツチを起動にし、制御棒引抜き開始し
て、曲線Cにそつて炉水温度が上昇し原子炉出力
を上昇する。 The above driving operation is shown in Fig. 2. At the same time as the condenser vacuum pump is started, the vacuum begins to rise along the curve A line. After stopping the vacuum pump, open the MS drain valve and increase the vacuum inside the reactor vessel along curve B. Dissolved oxygen in the reactor water is degassed by maintaining a vacuum in the reactor vessel for approximately 3 hours. When the dissolved oxygen concentration in the reactor water falls below 200 ppb, the mode switch is activated and the control rods begin to be withdrawn, the reactor water temperature rises along curve C and the reactor output increases.
以上の運転操作において、真空ポンプ起動か
ら、モードスイツチを起動に入れるまでに約5.5
時間を要す。この時間のうち、3時間は、主復水
器の真空上昇に要する時間である。この時間が原
子炉の稼働率を下げる原因になつており従来技術
の欠点であつた。 In the above operation, it takes about 5.5 seconds from starting the vacuum pump to turning on the mode switch.
It takes time. Of this time, 3 hours is the time required to raise the vacuum in the main condenser. This time was a drawback of the prior art, causing a reduction in the operating rate of the nuclear reactor.
本発明の目的は、従来真空脱気運転法であつた
起動時間の操作上の時間ロスを主復水器の真空上
昇と原子炉容器の真空上昇を同時に行うことによ
り、従来真空脱気運転法であつた起動操作時間の
短縮を図り、プラント稼働率を高める運転法を提
供することにある。
The purpose of the present invention is to reduce the operational time loss associated with the conventional vacuum degassing operation method by raising the vacuum of the main condenser and the reactor vessel at the same time. The purpose of this invention is to provide an operating method that shortens the start-up operation time and increases plant availability.
上記目的を達成するため、本発明は、原子炉容
器、タービン、主復水器を有する沸騰水型原子炉
において、主復水器と原子炉容器の気相部を連通
し、しかる後に、主復水器を負圧にするととも
に、原子炉容器内の炉水を撹拌する原子炉再循環
ポンプの運転にあわせて原子炉再循環系の冷却材
浄化系を運転して浄化水を原子炉容器の気相部に
スプレイさせながら、原子炉冷却材中の溶存酸素
を除去し、その後、原子炉を起動し、原子炉の出
力を上昇させることを特徴とするものである。
In order to achieve the above object, the present invention provides a boiling water nuclear reactor having a reactor vessel, a turbine, and a main condenser, in which the main condenser and the gas phase part of the reactor vessel are connected, and then the main In addition to creating negative pressure in the condenser, the coolant purification system of the reactor recirculation system is operated in conjunction with the operation of the reactor recirculation pump that stirs the reactor water in the reactor vessel, and purified water is pumped into the reactor vessel. Dissolved oxygen in the reactor coolant is removed by spraying it into the gas phase of the reactor, and then the reactor is started up and the output of the reactor is increased.
以下、本発明の実施例を第1図によつて説明す
る。従来技術と設備は同様であり、手順の相違点
のみを説明する。原子炉圧力容器まわり、タービ
ン廻りの系統構成が完了していることを確認した
のち、主蒸気隔離弁3,4および5を開とし、タ
ービンバイパス弁10を開とし、所内蒸気により
配管18より、タービングランド部の軸封シール
を行う。真空ポンプ12を起動し、主復水器9お
よび、タービン7,8および主蒸気配管2およ
び、原子炉容器気相部25の真空上昇を同時に開
始する。真空ポンプの上昇とともに、原子炉容器
気相部25は負圧になり、気相部の空気がパージ
される。真空ポンプ12の能力の限界に達したと
き、起動用エゼクター14を起動し、さらに高真
空をうる。この時点で、真空ポンプは停止し、起
動用エゼクター単独真空上昇となる。この時点
で、原子炉容器気相部は、50〜120mmHgabs程度
の高真空になつており、炉水24中の溶存酸素
は、徐々に、過飽和分の酸素がガスとなつて、気
相部25に脱気される。原子炉容器内真空度と炉
水中の過飽和分の溶存酸素が濃度平衡に達するの
に、約2時間を要する。これ以上脱気操作の必要
はなく、既に、炉水の溶存酸素濃度は200ppb以
下に低減されており、原子炉モードスイツチを起
動に入れ、制御棒引抜きを開始する。
Embodiments of the present invention will be described below with reference to FIG. The prior art and equipment are similar, and only the differences in procedure will be described. After confirming that the system configuration around the reactor pressure vessel and around the turbine has been completed, the main steam isolation valves 3, 4, and 5 are opened, the turbine bypass valve 10 is opened, and in-house steam is supplied from the pipe 18. Perform shaft sealing of the turbine gland. The vacuum pump 12 is started, and vacuum raising of the main condenser 9, the turbines 7 and 8, the main steam piping 2, and the reactor vessel gas phase section 25 is started at the same time. As the vacuum pump rises, the reactor vessel gas phase section 25 becomes under negative pressure, and the air in the gas phase section is purged. When the capacity of the vacuum pump 12 reaches its capacity limit, the starting ejector 14 is started to create an even higher vacuum. At this point, the vacuum pump stops, and the startup ejector alone raises the vacuum. At this point, the reactor vessel gas phase has reached a high vacuum of approximately 50 to 120 mmHgabs, and the supersaturated oxygen in the reactor water 24 gradually turns into gas, and the gas phase section 25 is degassed. It takes about two hours for the vacuum inside the reactor vessel and the supersaturated dissolved oxygen in the reactor water to reach concentration equilibrium. There is no need for further deaeration operations, and the dissolved oxygen concentration in the reactor water has already been reduced to below 200 ppb, so the reactor mode switch is turned on and control rod withdrawal begins.
炉水の温度が100℃以上になると、蒸気が発生
し、原子炉の圧力上昇を開始するためタービンバ
イパス弁10を閉じ、原子炉容器1を加圧し、昇
温する。この時点から、MSドレン隔離弁21,
22を開とし、MSドレン弁23を開として、主
蒸気配管内を緩気させかつ、蒸気ドレンを主復水
器に排出する。以際は、規定の出力上昇手順に従
い操作する。 When the temperature of the reactor water reaches 100° C. or more, steam is generated and the turbine bypass valve 10 is closed to start increasing the pressure of the reactor, pressurizing the reactor vessel 1 and raising the temperature. From this point on, the MS drain isolation valve 21,
22 is opened, and the MS drain valve 23 is opened to allow air to relax in the main steam pipe and discharge steam drain to the main condenser. In this case, operate according to the specified output increase procedure.
以上の操作手順を第3図に示す。復水器真空ポ
ンプ起動とともに、曲線A′によつて復水器の真
空上昇が始まる。また同時に、原子炉容器の真空
度も曲線B′にそつて上昇する。真空ポンプ起動
して、約2〜3時間で、炉水の酸素脱気は完了
し、原子炉起動に移る。 The above operating procedure is shown in FIG. As soon as the condenser vacuum pump starts, the condenser vacuum begins to rise according to curve A'. At the same time, the degree of vacuum in the reactor vessel also increases along curve B'. After starting the vacuum pump, deaeration of oxygen from the reactor water will be completed in about 2 to 3 hours, and the reactor will start up.
しかるのち、制御棒を引抜いて、上昇上圧し、
出力上昇する。本操作により、第4図に示す如
く、原子炉炉水中の溶存酸素は、大気飽和時の濃
度5ppmから、脱気により、0.2ppm即ち200ppb以
下に真空脱気され、しかるのち、起動上温するこ
とにより曲線Dにそつて定格運転中の平衡値Gに
達する。この脱気運転により、原子炉一次系を構
成するオーステナイト系ステンレス鋼の応力腐食
割れの感受性領域Fを通過することなく原子炉を
起動でき、原子炉の圧力バウンダリの健全性を維
持できる。なお、脱気運転しない場合は、曲線E
の特性となるので好ましくない。 After that, the control rod was pulled out and the pressure was applied upward.
Output increases. Through this operation, as shown in Figure 4, the dissolved oxygen in the reactor water is vacuum degassed from the concentration of 5 ppm at atmospheric saturation to 0.2 ppm, that is, 200 ppb or less, and then the temperature is increased during startup. As a result, the equilibrium value G during rated operation is reached along curve D. With this degassing operation, the reactor can be started without passing through the stress corrosion cracking susceptibility region F of the austenitic stainless steel that constitutes the reactor primary system, and the integrity of the pressure boundary of the reactor can be maintained. In addition, if deaeration operation is not performed, curve E
This is not preferable because it has the following characteristics.
さて、本発明の効果は、上気の脱気効果を達成
することはもちろん、第5図に示す如く、原子炉
起動時の起動時間の大巾短縮が可能となつた。原
子炉起動時の工程のクリテイカルパスとなるの
は、復水器真空ポンプ起動と、原子炉モードスイ
ツチ起動までの時間である。従来技術では、主復
水器の真空上昇に約2.5hr、原子炉圧力容器の真
空上昇に約3hrを要し、計5.5hrの原子炉起動まで
の時間を要していた。一方、本発明の運転によれ
ば、主復水器と原子炉容器の真空上昇を同時に達
成できるので、真空ポンプ起動から、モードスイ
ツチ起動まで、約3hrに短縮できた。この3hrの短
縮は1100MWe級プラントの場合、1回の起動に
つき約2090万円に相当する経済的メリツトを生
む。年2回の起動があるとすると、プラント寿命
30年間のうちには、約12億5千万円もの経済的効
果をもたらすことができる。 Now, the effects of the present invention include not only achieving the effect of degassing the upper air, but also making it possible to significantly shorten the start-up time when starting up the nuclear reactor, as shown in FIG. The critical path of the reactor startup process is the time between starting the condenser vacuum pump and starting the reactor mode switch. With the conventional technology, it took about 2.5 hours to raise the vacuum in the main condenser and about 3 hours to raise the vacuum in the reactor pressure vessel, for a total of 5.5 hours to start the reactor. On the other hand, according to the operation of the present invention, it was possible to raise the vacuum of the main condenser and the reactor vessel at the same time, so the time from starting the vacuum pump to starting the mode switch could be shortened to about 3 hours. In the case of a 1100MWe class plant, this 3hr reduction will result in an economic benefit equivalent to approximately 20.9 million yen per startup. If the plant is started up twice a year, the life of the plant is
Over a period of 30 years, it can bring about an economic effect of approximately 1.25 billion yen.
本発明のもうひとつの実施例として、第6図に
より説明する。本発明の実施例で説明した内容と
相違するところのみを示す。主復水器9と原子炉
圧力容器25の真空上昇を同時に開始する。主復
水器真空度の要求はタービン起動条件90mmHgabs
がありこの値は原子炉圧力が定格圧力に達するま
でに、真空上昇すればよい。一方、原子炉圧力容
器の真空度は、できるだけ早く、高真空にし、短
時間で、炉水脱気を行うことが必要となる。そこ
で本発明は、主復水器と原子炉容器の真空上昇と
同時に、原子炉再循環ポンプ20を運転し、炉水
の撹拌を行うこととあわせて、原子炉冷却材浄化
系(CUW系)を運転し、この浄化循環水を原子
炉圧力容器気相部にスプレイさせ、気液接触面積
を大として、真空脱気効果を高める。配管26よ
り取り出した炉水をCUWポンプ27で、再生熱
交換器28および非再生熱交換器29を介して、
浄化装置30で浄化した水を配管32を介して弁
33を開として、頂部スプレイノズル34より気
相部にスプレイする。この運転を行うことによ
り、炉水の溶存酸素が200ppb以下に達する時間
が、短縮されるため、原子炉起動モードスイツチ
を早く入れることができ、更に、起動時間の短縮
が可能となる。原子炉容器の頂部スプレイノズル
がCUW系と連接されていないプラントにおいて
は、残留熱除去法(RHR系)の頂度スプレイノ
ズルを介して、行うことができる。この際は、
RHR系のポンプを起動して、頂部スプレイモー
ド運転を行えばよい。 Another embodiment of the present invention will be explained with reference to FIG. Only the points that are different from those described in the embodiments of the present invention will be shown. Raising the vacuum of the main condenser 9 and the reactor pressure vessel 25 is started at the same time. Main condenser vacuum requirement is 90mmHgabs for turbine startup condition.
This value can be achieved by increasing the vacuum until the reactor pressure reaches the rated pressure. On the other hand, the degree of vacuum in the reactor pressure vessel needs to be raised to high vacuum as soon as possible, and reactor water must be degassed in a short time. Therefore, the present invention operates the reactor recirculation pump 20 and stirs the reactor water at the same time as the vacuum rises in the main condenser and reactor vessel. The purified circulating water is sprayed into the gas phase section of the reactor pressure vessel, increasing the gas-liquid contact area and enhancing the vacuum degassing effect. The reactor water taken out from the piping 26 is passed through the regenerative heat exchanger 28 and the non-regenerative heat exchanger 29 by the CUW pump 27.
The water purified by the purifier 30 is sprayed into the gas phase from the top spray nozzle 34 by opening the valve 33 through the pipe 32. By performing this operation, the time for dissolved oxygen in the reactor water to reach 200 ppb or less is shortened, so the reactor startup mode switch can be turned on quickly, and the startup time can be further shortened. In plants where the reactor vessel top spray nozzle is not connected to the CUW system, this can be done via the residual heat removal (RHR system) top spray nozzle. In this case,
Just start the RHR system pump and run it in top spray mode.
本発明の一実施例によれば、炉水のスプレイ脱
気効果により、脱気時間の短縮が図れるので、起
動時間の短縮に効果がある。 According to one embodiment of the present invention, the spray degassing effect of reactor water can reduce the degassing time, which is effective in shortening the start-up time.
本発明の他の実施例を第7図により説明する。
本発明は、万一、炉水の燃料が破損した場合の予
防対策を考慮した運転方法である。まず、燃料の
損傷の有無は、プラント停止中に、炉水中の核種
分析を行うことにより明確に把握できる。この場
合は、原子炉圧力容器と主復水器の真空上昇は、
独立に行う、原子炉圧力容器内のガスは気体放射
性廃棄物処理系で処理すべきである。 Another embodiment of the present invention will be described with reference to FIG.
The present invention is an operating method that takes preventive measures into consideration in the unlikely event that the fuel in the reactor water is damaged. First, the presence or absence of fuel damage can be clearly determined by analyzing the nuclide in the reactor water while the plant is shut down. In this case, the vacuum rise in the reactor pressure vessel and main condenser is
Separately, the gas in the reactor pressure vessel should be treated in a gaseous radioactive waste treatment system.
なお、原子炉起動前に炉水の核種分析を行い、
希ガスの存在がバツクグランドレベルである場合
は、原子炉圧力容器とタービン主復水器の真空上
昇を同時に行うことで、問題はない。しかし、真
空脱気操作中に、炉水中に溶解していたものが、
非凝縮性ガスとなつて出てくる場合を考慮してお
く必要がある。そのために本発明の他の実施例で
は、まず、主復水器の真空上昇を真空ポンプ12
で上昇する。同時に、主蒸気ライン2と弁3,4
および5とタービンバイパス弁10を開にし、原
子炉圧力容器内の気相部空気をパージする。 Furthermore, before reactor startup, a nuclide analysis of the reactor water was carried out.
If the presence of rare gas is at background level, there is no problem by raising the vacuum of the reactor pressure vessel and the turbine main condenser at the same time. However, during the vacuum degassing operation, substances dissolved in the reactor water
It is necessary to consider the case where the gas comes out as a non-condensable gas. To this end, in another embodiment of the present invention, the vacuum pump 12 first increases the vacuum in the main condenser.
rises with At the same time, main steam line 2 and valves 3 and 4
5 and the turbine bypass valve 10 are opened to purge the gas phase air in the reactor pressure vessel.
空気パージの途中で、放射能をモニターするた
めに、主蒸気配管2の原子炉圧力容器出口に、サ
ンプリングノズルを設け配管35を介して放射能
モニター装置37へ導き、連続モニターする。 In order to monitor radioactivity during the air purge, a sampling nozzle is provided at the reactor pressure vessel outlet of the main steam pipe 2 and guided to a radioactivity monitoring device 37 via a pipe 35 for continuous monitoring.
放射能が検知されると運転員に警報を発すると
ともにその信号により、主蒸気隔離弁(MSIV)
3および4が急速閉にするインターロツクを設け
ておく。MSIVが閉になると原子炉圧力容器の真
空脱気が達成されないので、先に主復水器9の真
空を上昇させ、起動用エゼクター14単独運転に
入り、活性炭吸着塔を有する気体処理設備16を
介して、運転できるようになつてから、MSドレ
ン隔離弁211,22を開としてMSドレン弁2
3をジヨギング運転をししかる後MSIVを開と
し、タービンバイパス弁10を開として、原子炉
の真空上昇を再開する。 If radioactivity is detected, an alert is issued to the operator and the signal is used to activate the main steam isolation valve (MSIV).
3 and 4 are provided with an interlock for quick closing. When the MSIV is closed, vacuum degassing of the reactor pressure vessel cannot be achieved, so the vacuum in the main condenser 9 is increased first, the start-up ejector 14 enters independent operation, and the gas processing equipment 16 having an activated carbon adsorption tower is activated. After the MS drain isolation valves 211 and 22 are opened, the MS drain valve 2 is opened.
After the jogging operation in step 3, the MSIV is opened, the turbine bypass valve 10 is opened, and the vacuum rise in the reactor is resumed.
本実施例によれば、放射性ガスを直接、排気筒
に放出することを防止でき、かつ、原子炉の真空
脱気が達成されるので、原子炉一次系のバウンダ
リーの健全性を確保すると同時に、万一の放射能
の放出を防止できる。 According to this embodiment, it is possible to prevent radioactive gas from being directly released into the stack, and vacuum deaeration of the reactor is achieved, so that the integrity of the boundary of the reactor primary system is ensured, and at the same time, It can prevent the release of radioactivity in the unlikely event.
本発明によれば、原子炉の起動時間の短縮が図
れるので、プラント稼働率の向上ができ、経済的
運転ができる効果がある。
According to the present invention, since the start-up time of the nuclear reactor can be shortened, the plant availability rate can be improved and the plant can be operated economically.
第1図は、本発明の運転操作に係る系統の概要
図、第2図は、従来技術の真空脱気運転を説明す
る特性図、第3図は、本発明の一実施例を説明す
る線図、第4図は、本発明の脱気効果を説明する
特性図、第5図は、従来技術と本発明の効果の説
明図、第6図は、本発明の他の実施例の系統図、
第7図は、本発明のさらに他の実施例の系統図で
ある。
1…原子炉容器、9…復水器、12…真空ポン
プ、14…起動用エゼクター、3,4…主蒸気隔
離弁、23…MSドレン弁、34…頂部スプレイ
ノズル、37…放射能モニター装置、B…原子炉
容器真空度、D…炉水溶存酸素濃度。
Fig. 1 is a schematic diagram of the system related to the operation of the present invention, Fig. 2 is a characteristic diagram explaining the vacuum degassing operation of the prior art, and Fig. 3 is a line diagram explaining one embodiment of the present invention. 4 is a characteristic diagram explaining the degassing effect of the present invention, FIG. 5 is a diagram explaining the effect of the prior art and the present invention, and FIG. 6 is a system diagram of another embodiment of the present invention. ,
FIG. 7 is a system diagram of still another embodiment of the present invention. 1... Reactor vessel, 9... Condenser, 12... Vacuum pump, 14... Starting ejector, 3, 4... Main steam isolation valve, 23... MS drain valve, 34... Top spray nozzle, 37... Radioactivity monitoring device , B... Reactor vessel vacuum degree, D... Reactor water dissolved oxygen concentration.
Claims (1)
騰水型原子炉において、前記主復水器と前記原子
炉容器の気相部を連通し、しかる後に、前記主復
水器を負圧にするとともに、前記原子炉容器内の
炉水を撹拌する原子炉再循環ポンプの運転にあわ
せて原子炉再循環系の冷却材浄化系を運転して浄
化水を原子炉容器の気相部にスプレイさせなが
ら、原子炉冷却材中の溶存酸素を除去し、その
後、原子炉を起動し、原子炉の出力を上昇させる
ことを特徴とする原子炉運転方法。1. In a boiling water reactor having a reactor vessel, a turbine, and a main condenser, the main condenser and the gas phase portion of the reactor vessel are communicated, and then the main condenser is brought into negative pressure. At the same time, in conjunction with the operation of the reactor recirculation pump that stirs the reactor water in the reactor vessel, the coolant purification system of the reactor recirculation system is operated to spray purified water into the gas phase part of the reactor vessel. A method of operating a nuclear reactor, characterized in that dissolved oxygen in a reactor coolant is removed while the reactor is being operated, and then the reactor is started up and the output of the reactor is increased.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58105688A JPS59231489A (en) | 1983-06-15 | 1983-06-15 | Method of operating nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58105688A JPS59231489A (en) | 1983-06-15 | 1983-06-15 | Method of operating nuclear reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS59231489A JPS59231489A (en) | 1984-12-26 |
| JPH049277B2 true JPH049277B2 (en) | 1992-02-19 |
Family
ID=14414338
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58105688A Granted JPS59231489A (en) | 1983-06-15 | 1983-06-15 | Method of operating nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS59231489A (en) |
-
1983
- 1983-06-15 JP JP58105688A patent/JPS59231489A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS59231489A (en) | 1984-12-26 |
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