JPH0361159B2 - - Google Patents
Info
- Publication number
- JPH0361159B2 JPH0361159B2 JP58018617A JP1861783A JPH0361159B2 JP H0361159 B2 JPH0361159 B2 JP H0361159B2 JP 58018617 A JP58018617 A JP 58018617A JP 1861783 A JP1861783 A JP 1861783A JP H0361159 B2 JPH0361159 B2 JP H0361159B2
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- heat exchanger
- pressure vessel
- boiler
- heat
- 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
- 238000007689 inspection Methods 0.000 claims description 17
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 17
- 230000000737 periodic effect Effects 0.000 claims description 16
- 238000009835 boiling Methods 0.000 claims description 15
- 239000000498 cooling water Substances 0.000 claims description 12
- 238000000034 method Methods 0.000 description 12
- 238000010586 diagram Methods 0.000 description 7
- 230000000694 effects Effects 0.000 description 3
- 238000013459 approach Methods 0.000 description 1
- 238000004891 communication Methods 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 230000007423 decrease Effects 0.000 description 1
- 238000013461 design Methods 0.000 description 1
- 238000007599 discharging Methods 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
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Control And Safety Of Cranes (AREA)
Description
【発明の詳細な説明】
〔発明の利用分野〕
本発明は自然循環型の沸騰水型原子炉、特に圧
力容器内に熱交換器を内蔵する自然循環型の沸騰
水型原子炉のシステム構成及び冷態停止後の却動
法に関するものである。Detailed Description of the Invention [Field of Application of the Invention] The present invention relates to a natural circulation boiling water reactor, particularly a system configuration and a natural circulation boiling water reactor having a built-in heat exchanger in a pressure vessel. This relates to a method for discharging after a cold shutdown.
一般に沸騰水型原子炉では、出力あるいは冷却
水流量の振動が時間とともに発散する不安定現象
を避けるような設計および運転を行なつている。
第１図は流量および出力の振動の様子を示したも
ので、隣接する波の振幅の比（減幅比）X2／X1
が１より小さければ安定である。一般に低流量、
高出力になるほど減幅比は大きくなり不安定側に
近づく。
In general, boiling water reactors are designed and operated to avoid unstable phenomena in which fluctuations in power output or cooling water flow rate diverge over time.
Figure 1 shows how the flow rate and output oscillate, and the ratio of the amplitudes of adjacent waves (attenuation ratio )
If is smaller than 1, it is stable. generally low flow,
As the output becomes higher, the attenuation ratio becomes larger and approaches the unstable side.
第２図は、自然循環型の沸騰水型原子炉の出力
と流量の関係および不安定領域を示したもので、
図の斜線領域が減幅比が１より大きくなる不安定
領域である。そして圧力が低くなるほどこの不安
定領域は、図中、下方に拡がる傾向がある。従つ
て低圧および低流量では安定性余裕が小さい。こ
のため自然循環型原子炉では第３図に示すよう
に、原子炉圧力容器１に予熱器２を接続し、これ
で炉水３を熱して原子炉を昇温・昇圧して安定性
余裕を大きくしてから出力を上昇させるという起
動法を採用している。４は炉心である。原子炉を
昇温・昇圧するには、この他に外部から蒸気を吹
き込む方法もある。 Figure 2 shows the relationship between output and flow rate and the unstable region of a natural circulation boiling water reactor.
The shaded area in the figure is an unstable area where the width reduction ratio is greater than 1. As the pressure decreases, this unstable region tends to expand downward in the figure. Therefore, the stability margin is small at low pressures and low flow rates. For this reason, in a natural circulation reactor, as shown in Figure 3, a preheater 2 is connected to the reactor pressure vessel 1, which heats the reactor water 3 to raise the temperature and pressure of the reactor, thereby increasing the stability margin. It uses a startup method that increases the output and then increases the output. 4 is the reactor core. Another way to raise the temperature and pressure of a nuclear reactor is to inject steam from outside.
安定性余裕を大きくする別の方法としては、第
４図に示すように圧力容器１の外部に再循環系５
を接続して冷却水３をポンプＰで強制循環させる
方法がある。第５図は、このような強制循環型の
沸騰水型原子炉の起動法を示した起動マツプで、
冷却水を定格流量の20％流量でポンプ運転を行な
つて循環させながら出力を上昇させる方法を用い
ている。第６図に示すように、このような方法を
用いることにより、起動時には自然循環曲線上で
運転したときよりも安定性余裕を大きくすること
が可能である。 Another way to increase the stability margin is to install a recirculation system 5 outside the pressure vessel 1, as shown in FIG.
There is a method of forcibly circulating the cooling water 3 with a pump P by connecting the Figure 5 is a startup map showing the startup method for such a forced circulation boiling water reactor.
A method is used to increase output while circulating cooling water by operating the pump at 20% of the rated flow rate. As shown in FIG. 6, by using such a method, it is possible to have a larger stability margin at startup than when operating on a natural circulation curve.
さて第７図は、圧力容器１内に熱交換器６を内
蔵する自然循環型の沸騰水型原子炉の構成を示す
概略図である。この原子炉では、炉心４を通つた
冷却水３はライザ７の周囲に設けられた熱交換器
６に熱を与え、サブクール水となつて炉心入口か
ら炉心４に入るように自然循環される。このよう
に熱交換器を内蔵した理由は、冷却水３が圧力容
器１内だけを流動するようにして一次系（圧力容
器内）と二次系（熱交換器側）を完全に隔離し、
安全性の高い構造とするためである。８は熱交換
器６から熱を受け取る二次熱交換器である。 Now, FIG. 7 is a schematic diagram showing the configuration of a natural circulation type boiling water reactor in which a heat exchanger 6 is built in a pressure vessel 1. In this nuclear reactor, the cooling water 3 passing through the core 4 gives heat to the heat exchanger 6 provided around the riser 7, and is naturally circulated as subcooled water to enter the core 4 from the core inlet. The reason for incorporating the heat exchanger in this way is that the cooling water 3 flows only within the pressure vessel 1, completely separating the primary system (inside the pressure vessel) and the secondary system (on the heat exchanger side).
This is to provide a highly safe structure. A secondary heat exchanger 8 receives heat from the heat exchanger 6.
このような原子炉においては、起動時の安定性
余裕を向上させるために前述の如き予熱系の接続
又は強制的再循環ループの接続といういずれかの
方法をとることは、冷却水を圧力容器内に隔離す
るという上記目的から、いずれも採用されない。
このため従来このような原子炉では起動時に不安
定とならないように出力を極めてゆつくり上昇さ
せなければならず、起動方法が複雑となるという
問題があつた。 In such a reactor, in order to improve the stability margin at startup, it is necessary to connect the preheating system as described above or to connect the forced recirculation loop, which will reduce the cooling water inside the pressure vessel. None of these will be adopted due to the above purpose of isolating people.
For this reason, in conventional nuclear reactors of this type, the output had to be increased extremely slowly to avoid instability during startup, which posed a problem in that the startup method became complicated.
本発明の目的は、上記した熱交換器内蔵式自然
循環型沸騰水原子炉において、従来の問題点を改
善し、起動時の安定性余裕を改善できる冷態停止
後の起動法及びその原子炉システムを提供するこ
とにある。
The object of the present invention is to provide a method for starting up the reactor after a cold shutdown, which can improve the stability margin at startup by improving the conventional problems in the above-mentioned natural circulation boiling water reactor with a built-in heat exchanger. The goal is to provide a system.
本発明による原子炉起動法は、原子炉圧力容器
内に熱交換器を内蔵する自然循環型の沸騰水型原
子炉の冷態停止後の起動の際、原子炉圧力容器外
に備えられている定期点検時熱供給用ボイラから
の熱を前記熱交換器を介して原子炉圧力容器内の
冷却水に予め供給することを特徴するものであ
り、またそのための本発明による原子炉システム
は、上記自然循環型沸騰水原子炉において上記熱
交換器の二次系配管又はそれと熱交換関係にある
三次系配管と上記定期点検時熱供給用ボイラから
の配管とを接続する開閉切換自在な弁を設けたこ
とを特徴とするものである。
The nuclear reactor startup method according to the present invention provides a heat exchanger installed outside the reactor pressure vessel during startup after a cold shutdown of a natural circulation boiling water reactor that has a built-in heat exchanger inside the reactor pressure vessel. The reactor system according to the present invention is characterized in that heat from the boiler for heat supply during periodic inspection is supplied in advance to the cooling water in the reactor pressure vessel via the heat exchanger, and the reactor system for this purpose is characterized by the above-mentioned In a natural circulation boiling water reactor, a valve that can be switched open and closed is provided to connect the secondary system piping of the heat exchanger or the tertiary system piping that is in a heat exchange relationship with the secondary system piping and the piping from the boiler for heat supply during periodic inspections. It is characterized by:
以下、本発明を実施例によつて詳細に説明す
る。第８図において１は原子炉圧力容器、３は冷
却水、４は炉心である。６は圧力容器１内にライ
ザー７の周りに内蔵された一次熱交換器、８は原
子炉圧力容器１の外に設けられた二次熱交換器で
ある。９は定期検査時熱供給用ボイラであつて、
一次熱交換器６と二次熱交換器８を結ぶ二次系配
管１０に三方弁１１によつて接続されている。１
２は二次系配管１０に三方弁１１で接続されたバ
イパス、１３はポンプである。
Hereinafter, the present invention will be explained in detail with reference to Examples. In FIG. 8, 1 is a reactor pressure vessel, 3 is cooling water, and 4 is a reactor core. 6 is a primary heat exchanger built into the pressure vessel 1 around the riser 7, and 8 is a secondary heat exchanger provided outside the reactor pressure vessel 1. 9 is a boiler for supplying heat during regular inspections,
It is connected to a secondary system piping 10 connecting the primary heat exchanger 6 and the secondary heat exchanger 8 via a three-way valve 11. 1
2 is a bypass connected to the secondary system piping 10 by a three-way valve 11, and 13 is a pump.
さて、原子炉の運転は大別すると(1)通常運転
時、(2)定期点検時、(3)起動時の三つになる。以
下、この三つの運転時における上記原子炉システ
ムの動作を第９、第１０及び第１１図により説明
する。これらの図において、各三方弁１１の黒く
塗つた部分および黒く塗つてない部分は、夫々そ
の部分の流路が閉及び開の状態にあることを示し
ている。 Now, the operation of a nuclear reactor can be roughly divided into three parts: (1) normal operation, (2) periodic inspection, and (3) startup. Hereinafter, the operation of the above-mentioned nuclear reactor system during these three operations will be explained with reference to FIGS. 9, 10, and 11. In these figures, the black-colored portions and non-black-colored portions of each three-way valve 11 indicate that the flow passages in those portions are in the closed and open states, respectively.
第９図は通常運転時の様子を示したものであつ
て、定期検査用ボイラ９側の流路は全て閉とな
り、また二次系配管部に設けたバイパス１２も閉
であり、一次熱交換器６と二次熱交換器８とは連
通接続される。 Figure 9 shows the situation during normal operation, in which all the flow paths on the boiler 9 side for periodic inspection are closed, the bypass 12 provided in the secondary system piping is also closed, and the primary heat exchanger is closed. The vessel 6 and the secondary heat exchanger 8 are connected in communication.
第１０図は定期点検時の様子を示したものであ
り、三方弁は一次熱交換器６側とバイパス１２お
よび定期検査用ボイラ９側の一部を閉とすること
により、定期検査用ボイラ９で発生した熱を直接
二次熱交換器８に送ることができる。 Figure 10 shows the situation during periodic inspection, and the three-way valve closes the primary heat exchanger 6 side, the bypass 12, and a part of the periodic inspection boiler 9 side. The heat generated can be sent directly to the secondary heat exchanger 8.
第１１図は起動時の様子を示したもので、各三
方弁１１を図に示すような開閉状態にすることに
より、原子炉の定期検査時において原子炉にかわ
り、熱供給を行なうためのボイラ９で発生した熱
を一次熱交換器６を介して圧力容器１中の冷却水
に供給し、これにより、冷態停止後の原子炉起動
時に予め原子炉を昇温・昇圧することができ、起
動時の安定性余裕を改善することが可能である。 Figure 11 shows the state at startup. By opening and closing each three-way valve 11 as shown in the figure, the boiler can be used to supply heat instead of the reactor during periodic reactor inspections. The heat generated in step 9 is supplied to the cooling water in the pressure vessel 1 through the primary heat exchanger 6, thereby making it possible to raise the temperature and pressure of the reactor in advance when starting the reactor after a cold shutdown. It is possible to improve the stability margin during startup.
したがつて、上記のような自然循環型原子炉シ
ステムとその起動法を用いれば、圧力容器内の圧
力を上げて安定性余裕が大きくなつてから制御棒
を引き抜いて出力の上昇を開始することができ
る。第１２図は、このことを具体的に示した計算
結果である。従来の方法によつて低圧で原子炉を
起動する場合には、出力を零から徐々に上昇させ
ると減幅比がいつたん上昇し安定性余裕が小さく
なる。これに対して本発明になる起動法を用いれ
ば、炉内圧力が予め高くなつているため減幅比の
増加は小さい。例えば１気圧で起動した場合には
減幅比は１より大きくて不安定であるが、本発明
によれば圧力を上昇させることによつて減幅比が
小さくなる。例えば20気圧では減幅比は0.35とな
り、安定性余裕を大きくすることができる。 Therefore, by using the natural circulation reactor system and its startup method as described above, it is possible to increase the pressure inside the pressure vessel and increase the stability margin before withdrawing the control rods and starting to increase the output. I can do it. FIG. 12 shows calculation results specifically showing this. When starting a nuclear reactor at low pressure using the conventional method, when the output is gradually increased from zero, the reduction ratio gradually increases and the stability margin becomes smaller. On the other hand, if the startup method according to the present invention is used, the increase in width reduction ratio is small because the pressure inside the furnace is already high. For example, when starting at 1 atmosphere, the width reduction ratio is larger than 1 and is unstable, but according to the present invention, the width reduction ratio becomes smaller by increasing the pressure. For example, at 20 atm, the width reduction ratio is 0.35, which increases the stability margin.
本実施例では通常の原子炉設備に大幅な設計変
更を加えることは不要であるからコストが低くな
る利点がある。 This embodiment has the advantage of lower costs because it is not necessary to make any major design changes to ordinary nuclear reactor equipment.
第１３図は、他の実施例を示すもので、前記の
実施例との相違点は、更に三次熱交換器１４を設
け、二次熱交換器８と三次熱交換器１４とを結ぶ
三次系配管１５に三方弁１１で定期検査用ボイラ
９及びバイパス１２を接続したことにある。１６
はポンプである。この実施例における通常運転
時、定期点検時及び起動時の夫々の運転態様は前
記実施例に準じて明らかであろう。この実施例で
は定期検査時用のボイラ９が三次系配管に接続さ
れているため、万一、一次熱交換器６で細管破断
等の事故が生じた場合でも、圧力容器内冷却水は
定期検査用ボイラ９に流入しないという利点があ
る。 FIG. 13 shows another embodiment, and the difference from the previous embodiment is that a tertiary heat exchanger 14 is further provided, and a tertiary system connecting the secondary heat exchanger 8 and the tertiary heat exchanger 14 is provided. The boiler 9 for periodic inspection and the bypass 12 are connected to the piping 15 by a three-way valve 11. 16
is a pump. The operating modes of this embodiment during normal operation, periodic inspection, and start-up will be clear according to the previous embodiments. In this embodiment, the boiler 9 for periodic inspection is connected to the tertiary system piping, so even if an accident such as a capillary rupture occurs in the primary heat exchanger 6, the cooling water in the pressure vessel can be inspected regularly. This has the advantage that it does not flow into the boiler 9.
本発明によれば、自然循環型の沸騰水型原子炉
の起動時に圧力容器内を予め昇温・昇圧できるの
で安定性余裕を改善することができ、しかも通常
運転及び定期点検も全く支障なく行うことができ
るという効果がある。
According to the present invention, since the temperature and pressure inside the pressure vessel can be raised in advance when starting up a natural circulation boiling water reactor, the stability margin can be improved, and normal operation and periodic inspections can be carried out without any problems. It has the effect of being able to
第１図は沸騰水型原子炉の流量及び出力の振動
の様子を示す図、第２図は、自然循環型原子炉の
運転曲線、第３図は予熱系を有する自然循環型原
子炉の構成を示す概略図、第４図は強制循環型原
子炉の構成を示す概略図、第５図は強制循環型原
子炉の起動法を示すプラント起動曲線、第６図は
強制循環型原子炉の運転曲線、第７図は熱交換器
内蔵自然循環型原子炉の構成を示す概略図、第８
図は本発明の実施例を示すシステム構成図、第９
図、第１０図、第１１図は該実施例の動作図、第
１２図は該実施例に係る効果を説明するための出
力−減幅比特性図、第１３図は本発明の他の実施
例を示すシステム構成図である。
１……原子炉圧力容器、２……予熱器、３……
冷却水、４……炉心、５……再循環系、６……内
蔵熱交換器、７……ライザー、８……二次熱交換
器、９……定期検査用ボイラ、１０……二次系配
管、１１……三方弁、１２……バイパス、１３…
…ポンプ、１４……三次熱交換器、１５……三次
系配管、１６……ポンプ。
Figure 1 shows the flow rate and output fluctuations of a boiling water reactor, Figure 2 shows the operating curve of a natural circulation reactor, and Figure 3 shows the configuration of a natural circulation reactor with a preheating system. Figure 4 is a schematic diagram showing the configuration of a forced circulation reactor, Figure 5 is a plant startup curve showing the startup method of a forced circulation reactor, and Figure 6 is the operation of a forced circulation reactor. curve, Figure 7 is a schematic diagram showing the configuration of a natural circulation reactor with a built-in heat exchanger, Figure 8
Figure 9 is a system configuration diagram showing an embodiment of the present invention.
10 and 11 are operation diagrams of this embodiment, FIG. 12 is an output-attenuation ratio characteristic diagram for explaining the effects of this embodiment, and FIG. 13 is another embodiment of the present invention. FIG. 1 is a system configuration diagram showing an example. 1... Reactor pressure vessel, 2... Preheater, 3...
Cooling water, 4...Core, 5...Recirculation system, 6...Built-in heat exchanger, 7...Riser, 8...Secondary heat exchanger, 9...Boiler for periodic inspection, 10...Secondary System piping, 11... Three-way valve, 12... Bypass, 13...
...Pump, 14...Tertiary heat exchanger, 15...Tertiary system piping, 16...Pump.
Claims (1)
炉圧力容器外に定期点検時熱供給用ボイラを備え
た自然循環型沸騰水原子炉システムの冷態停止後
の起動の際に、前記定期点検時熱供給用ボイラか
らの熱を前記熱交換器を介して原子炉圧力容器内
の冷却水に予め供給することを特徴とする自然循
環型の沸騰水型原子炉の起動法。 ２ 原子炉圧力容器内に熱交換器を内蔵し、原子
炉圧力容器外に定期点検時熱供給用ボイラを備え
た自然循環型の沸騰水型原子炉システムにおい
て、前記熱交換器の二次系配管又はそれと熱交換
関係にある三次系配管と前記定期点検時熱供給用
ボイラからの配管とを接続する開閉切換自在の弁
を設けたことを特徴とする自然循環型の沸騰水型
原子炉システム。[Claims] 1. After cold shutdown of a natural circulation boiling water reactor system that has a heat exchanger built into the reactor pressure vessel and a boiler for supplying heat during periodic inspections outside the reactor pressure vessel. A natural circulation boiling water nuclear reactor characterized in that, upon startup, heat from the boiler for heat supply during periodic inspections is previously supplied to cooling water in the reactor pressure vessel via the heat exchanger. How to start. 2. In a natural circulation boiling water reactor system that has a heat exchanger built into the reactor pressure vessel and a boiler for supplying heat during periodic inspections outside the reactor pressure vessel, the secondary system of the heat exchanger A natural circulation boiling water reactor system, characterized in that a valve that can be switched open and closed connects piping or tertiary system piping in a heat exchange relationship with the tertiary system piping and piping from the boiler for heat supply during periodic inspections. .
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58018617A JPS59143997A (en) | 1983-02-07 | 1983-02-07 | Boiling water reactor startup method and system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58018617A JPS59143997A (en) | 1983-02-07 | 1983-02-07 | Boiling water reactor startup method and system |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS59143997A JPS59143997A (en) | 1984-08-17 |
| JPH0361159B2 true JPH0361159B2 (en) | 1991-09-18 |
Family
ID=11976577
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58018617A Granted JPS59143997A (en) | 1983-02-07 | 1983-02-07 | Boiling water reactor startup method and system |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS59143997A (en) |
Families Citing this family (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5271044A (en) * | 1991-03-14 | 1993-12-14 | Hitachi, Ltd. | Boiling water nuclear reactor and start-up process thereof |
| JP4785558B2 (en) * | 2006-02-24 | 2011-10-05 | 日立Ｇｅニュークリア・エナジー株式会社 | Reactor monitoring device |
| JP4850537B2 (en) * | 2006-02-27 | 2012-01-11 | 日立Ｇｅニュークリア・エナジー株式会社 | Temperature detector for natural circulation boiling water reactor |
| JP2007232503A (en) * | 2006-02-28 | 2007-09-13 | Hitachi Ltd | Reactor system and reactor control method |
| JP4916569B2 (en) * | 2010-09-17 | 2012-04-11 | 日立Ｇｅニュークリア・エナジー株式会社 | Reactor system and reactor control method |
-
1983
- 1983-02-07 JP JP58018617A patent/JPS59143997A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS59143997A (en) | 1984-08-17 |
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