JPS6049278B2 - Boiling water reactor safety protection method - Google Patents
Boiling water reactor safety protection methodInfo
- Publication number
- JPS6049278B2 JPS6049278B2 JP55017521A JP1752180A JPS6049278B2 JP S6049278 B2 JPS6049278 B2 JP S6049278B2 JP 55017521 A JP55017521 A JP 55017521A JP 1752180 A JP1752180 A JP 1752180A JP S6049278 B2 JPS6049278 B2 JP S6049278B2
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- water level
- set point
- safety protection
- main steam
- 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
Links
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)
Description
【発明の詳細な説明】
発明の技術分野
本発明は、沸騰木型原子炉の原子炉水位信号に基き、
原子炉保護機能を作動させる沸騰木型原子炉の安全保護
方法に関する。DETAILED DESCRIPTION OF THE INVENTION Technical Field of the Invention The present invention is based on a reactor water level signal of a boiling wood reactor.
This invention relates to a safety protection method for a boiling wood reactor that activates a reactor protection function.
発明の技術的背景とその問題点
一般に、沸騰木型原子炉を保護するために設けられた
いわゆる工学的安全施設のうち、原子炉水位の異常変化
を検出して作動するものは、原子炉運転時の通常水位よ
り低水位側にも幾つかの水位設定点を設け、水位がこれ
らの設定点に達すると、定められた安全施設を作動させ
るようになつている。Technical background of the invention and its problems In general, among the so-called engineering safety facilities installed to protect boiling wood reactors, those that operate by detecting abnormal changes in the reactor water level are A number of water level set points are also provided below the normal water level, and when the water level reaches these set points, certain safety facilities are activated.
例えば先ず原子炉スクラムを生起させるとともに、主
蒸気隔離弁以外の隔離弁の閉鎖等を行なわせる設定点が
設けられ、この設定点より低水位側に主蒸気隔離弁の閉
鎖、高圧炉心スプレィ系の起動、原子炉隔離時冷却系の
起動および再循環ポンプの停止を行なわせる設定点が設
けられ、更にこの設定点より低水位側に非常用炉心冷却
系（以下ＥＣＣＳという）の諸設備を起動させる設定点
が設）けられている。For example, a set point is established that first causes a reactor scram and closes isolation valves other than the main steam isolation valve, and below this set point, the main steam isolation valve closes and the high-pressure core spray system closes. A set point is provided for starting, starting the reactor isolation cooling system, and stopping the recirculation pump, and also starts various equipment of the emergency core cooling system (hereinafter referred to as ECCS) at a lower water level than this set point. A set point is established.
このような設備を有する原子力発電プラントにおいて
は、運転時に何等かの原因て炉水位の低下が生じると、
炉水量の減少に応じて炉水位が上記した設定点に達した
とき、各設定点に対応する保・護機能が作動し、炉水位
をはじめとする原子炉の各種パラメータを安全側に誘導
する。In nuclear power plants with such equipment, if the reactor water level drops for some reason during operation,
When the reactor water level reaches the above set points as the amount of reactor water decreases, the protection functions corresponding to each set point are activated, guiding various reactor parameters including the reactor water level to the safe side. .
しかしながら、上記した工学的安全施設を有する原子力
発電プラントにおいても、特に定格出力運転中に発電機
負荷遮断が生じた場合、あるいはタービントリップによ
り主蒸気止弁が全閉した場合等には炉水位の初期変動（
低下）量が大きく、場合によつては上記した最低の水位
設定点に達し、ＥＣＣＳの作動に至る可能性があること
がわかつた。However, even in nuclear power plants that have the above-mentioned engineered safety facilities, reactor water level may drop, especially when generator load shedding occurs during rated output operation or when the main steam stop valve is fully closed due to a turbine trip. Initial variation (
It was found that the amount of water drop) was large and could in some cases reach the minimum water level set point mentioned above, leading to activation of the ECCS.
第２図は、発電機負荷遮断が生じた場合の原子炉の各種
パラメータの過渡的変化を示したもので、第２図ａにお
いて曲線Ａ１は炉心流量、伐は給水流量、Ｃ１は原子炉
蒸気量、Ｄ１は中性子束の各量の百分率変化を表わして
いる。Figure 2 shows transient changes in various reactor parameters when generator load shedding occurs. In Figure 2a, curve A1 is the core flow rate, curve is the feed water flow rate, and C1 is the reactor steam. The quantity D1 represents the percentage change in each quantity of neutron flux.
第２図ｂにおいては曲線Ｅ１は原子炉圧力、Ｆ１は原子
炉水位の各定格値を０とした変化状況を表わしており、
特に原子炉水位Ｆ１の、過渡状態初期における低下が著
しいことが明らかである。水位低下が大きく、上記した
最低の設定点に達し、ＥＣＣＳの作動に至るとすれば、
本来ＥＣＣＳは一次系配管破断による冷却材喪失事故を
想定した安全設備であり、作動後の復帰も煩雑となるた
め、過渡的な水位変動によるＥＣＣＳ起動の危険性は、
極力回避しておくことが望ましい。In Figure 2b, the curve E1 represents the reactor pressure, and the curve F1 represents the changes in the reactor water level with each rated value set to 0.
In particular, it is clear that the reactor water level F1 decreases significantly at the beginning of the transient state. If the water level drop is large enough to reach the minimum set point mentioned above and trigger the ECCS, then
ECCS is originally a safety device that assumes an accident in which coolant is lost due to a rupture in the primary system piping, and it is complicated to restore it after activation, so the risk of ECCS activation due to transient water level fluctuations is
It is desirable to avoid this as much as possible.
発明の目的
本発明は、原子力発電所の異常時に発生する原子炉水位
の変動幅を抑制して、保護機能の無用な作動を回避する
ことができる沸騰水型原子炉の安全保護方法を提供する
ことを目的とする発明の概要
本発明においては、原子炉通常運転時における原子炉圧
力容器内の炉水位の下限より低水位側に向つて、低水位
アラームを指令する第４の水位設定点と、原子炉スクラ
ム信号を起生するとともに主蒸気隔離弁以外の隔離弁の
閉鎖を指令する第３、の水位設定点と、主蒸気隔離弁の
閉鎖、高圧炉心スプレィ系の起動ならびに原子炉隔離時
冷却系の起動をそれぞれ指令する第２の水位設定点と、
非常用炉心冷却系の起動を指令する第１の水位設定点と
を上記原子炉圧力容器に上記の順序に設け、Ｚ炉水位が
上記第１乃至第４の各設定点に到達したとき、第１乃至
第４の各設定点に対応する各安全保護手段を作動させる
沸騰水型原子炉の安全保護方法において、炉水位が、第
３の水位設定点まで低下したとき、主蒸気隔離弁以外の
隔離弁の閉鎖とあわせて、原子炉に設けられた再循環ポ
ンプの運転を停止させて上記目的を達成している。Purpose of the Invention The present invention provides a safety protection method for a boiling water reactor that can suppress the range of fluctuations in reactor water level that occurs during abnormalities in a nuclear power plant and avoid unnecessary activation of protection functions. SUMMARY OF THE INVENTION The present invention provides a fourth water level set point for commanding a low water level alarm, which is set toward a lower water level than the lower limit of the reactor water level in the reactor pressure vessel during normal reactor operation. , a third water level set point that generates a reactor scram signal and commands the closure of isolation valves other than the main steam isolation valve, and the closure of the main steam isolation valve, startup of the high pressure core spray system, and reactor isolation. a second water level set point for respectively commanding activation of the cooling system;
A first water level set point for commanding the activation of the emergency core cooling system is provided in the reactor pressure vessel in the above order, and when the Z reactor water level reaches each of the first to fourth set points, In a boiling water reactor safety protection method that operates each safety protection means corresponding to each of the first to fourth set points, when the reactor water level drops to the third water level set point, In addition to closing the isolation valve, the operation of the recirculation pump installed in the reactor is stopped to achieve the above objective.
発明の実施例本発明の一実施例について、第１図を参照
しながら説明する。Embodiment of the Invention An embodiment of the present invention will be described with reference to FIG.
第１図において、沸騰水型原子炉の圧力容器１の内部に
は、炉心２を囲んで、圧力容器１の外部に設置された再
循環ポンプとその配管（いずれもフ図示省略）に連なる
ジェットポンプ３が設けられ、これらが炉水４に浸漬さ
れている。In FIG. 1, inside a pressure vessel 1 of a boiling water reactor, there are jets that surround a reactor core 2 and are connected to a recirculation pump and its piping (both are not shown), which are installed outside the pressure vessel 1. A pump 3 is provided, which is immersed in reactor water 4.
炉心２の上方には、気水分離器５に続いて蒸気乾燥器６
とそのスカート７が設けられ、炉心２における核反応に
より加熱された炉水４から発生した蒸気を処１理してい
る。原子炉の通常運転時における炉水４の水位変動は、
第１図の右端に示すように、上限Ｌと下限しの間にある
が、原子炉に生じた何等かの異常状態に基く炉水位の変
動を検出する水位設定点と・して、上限Ｌ６より高水位
側に、高水位アラームを発す設定点レと、タービントリ
ップを指令する信号を発する設定点Ｌ８がこの順に設け
られている。Above the core 2 is a steam dryer 6 following a steam separator 5.
and its skirt 7 are provided to treat steam generated from reactor water 4 heated by the nuclear reaction in the reactor core 2. Fluctuations in the level of reactor water 4 during normal operation of the reactor are as follows:
As shown on the right side of Figure 1, the upper limit L6 is located between the upper limit L and the lower limit, and is used as the water level setting point for detecting fluctuations in the reactor water level based on some abnormal condition that occurs in the reactor. On the higher water level side, a set point L8 which issues a high water level alarm and a set point L8 which issues a signal instructing a turbine trip are provided in this order.
また下限Ｌ５より低水位側には、先す低水位アラームを
発する設定点Ｌ４が設けられ、この設定点Ｌ４より低水
位側に、原子炉スクラムを起動させる設定点であると同
時に、主蒸気隔離弁以外の隔離弁（図示省略）の閉鎖と
、再循環ポンプの停止とを指令する信号を発する設定点
Ｌ３が設けられている。Further, on the lower water level side than the lower limit L5, a set point L4 is provided that first issues a low water level alarm. A set point L3 is provided which provides a signal commanding the closure of an isolation valve other than the valve (not shown) and the stoppage of the recirculation pump.
設定点Ｌ３より低水位側には設定点Ｌ２があり、主蒸気
隔離弁（図示省略）の閉鎖、高圧炉心スプレィ系（図示
省略）の起動、および原子炉隔離時冷却系（図示省略）
の起動を指令する信号を発生する。There is a set point L2 on the lower water level side than the set point L3, which closes the main steam isolation valve (not shown), starts the high-pressure core spray system (not shown), and reactor isolation cooling system (not shown).
Generates a signal to start the
更に設定点！より低水位側にＥＣＣＳｌすなわち低圧炉
心スプレィ系（図示省略）、低圧注水系（図示省略）お
よび自動減圧系（図示省略）の起動信号を発する設定点
レが設けられている。原子力発電所の運転中に、炉水位
が下限Ｋｇと上限Ｌ６の範囲外に変動し、設定点Ｌ７，
ｌ−５３、あるいは設定点Ｌ４，Ｌ３，Ｌ２，［４の各
水位に達すると、上記した各設定点に対応する固有の安
全保護設備が作動する。例えば炉水位が低下して設定点
！に到達すると、原子炉がスクラムするとともに、主蒸
気隔離弁以外の隔離弁が閉鎖され、再循環ポンプが停止
する。第３図は、本実施例を適用した場合に、発電機負
荷遮断が発生した後の、原子炉の各種パラメータの過渡
的変化を示したもので、第３図ａにおいて曲線〜は炉心
流量、式は給水流量、Ｃ２は原子炉蒸気量、Ｄ２は中性
子束の各量の百分率変化を表わしている。More set points! On the lower water level side, a set point is provided for issuing a start signal for ECCSl, that is, a low pressure core spray system (not shown), a low pressure water injection system (not shown), and an automatic depressurization system (not shown). During operation of a nuclear power plant, the reactor water level fluctuates outside the range between the lower limit Kg and the upper limit L6, and the set point L7,
1-53, or each of the set points L4, L3, L2, [4, the specific safety protection equipment corresponding to each set point described above is activated. For example, the reactor water level drops to the set point! When , the reactor scrams, isolation valves other than the main steam isolation valve are closed, and the recirculation pumps are stopped. FIG. 3 shows transient changes in various parameters of the reactor after generator load shedding occurs when this embodiment is applied. In FIG. The formula represents the feed water flow rate, C2 represents the reactor steam amount, and D2 represents the percentage change in each amount of neutron flux.
第３図ｂにおいては実線Ｅ２は原子炉圧力、Ｆ２は原子
炉水位の各定格値を０とした変化曲線を表わし、破線Ｆ
１は、設定点Ｌ３に替えて設定点Ｌ２において再循環ポ
ンプの停止を行なつた場合の、実線Ｆ２に対応する変化
を比較のために示したもので、第２図ｂの曲線Ｆ１に対
応するものてあり、実線Ｆ２と破線Ｆ１を対比すれは、
本実施例における原子炉水位の変動低下量が改善されて
いることがわかる。またタービントリップにより主蒸気
止弁（図示省略）が全閉した場合も同一の傾向を示す。
なお再循環ポンプの停止は、設定点しの発する信号と、
主蒸気加減弁（図示省略）の急閉指令信号との論理積に
よつて行なうようにしてもよい。In Figure 3b, the solid line E2 represents the reactor pressure, F2 represents the change curve with each rated value of the reactor water level set to 0, and the broken line F
1 shows for comparison the change corresponding to the solid line F2 when the recirculation pump is stopped at the set point L2 instead of the set point L3, which corresponds to the curve F1 in Figure 2 b. Comparing the solid line F2 and the broken line F1,
It can be seen that the amount of reduction in fluctuation of the reactor water level in this example is improved. The same tendency is also shown when the main steam stop valve (not shown) is fully closed due to a turbine trip.
The recirculation pump stops depending on the signal emitted by the set point and
This may be performed by logical product with a quick-closing command signal of a main steam control valve (not shown).
発明の効果
以上の説明から明らかなように、本発明の沸騰水型原子
炉の安全保護方法によれば、炉水位の一過性の変動に基
因するＥＣＣＳの作動機会を回避低減することができる
。Effects of the Invention As is clear from the above explanation, according to the boiling water reactor safety protection method of the present invention, it is possible to avoid and reduce the chance of ECCS activation due to temporary fluctuations in reactor water level. .
第１図は本発明の一実施例に係る炉水位の設定点を示す
模式図、第２図は従来の原子炉の各パラメータの過渡変
化を表わす線図、第３図は本発明の原子炉の各パラメー
タの過渡変化を表わず線図である。
１・・・・・・原子炉圧力容器、４・・・・・・炉水、
Ｌｌ，Ｌ２，Ｌ３，Ｌ４・・・・・・水位設定点。Fig. 1 is a schematic diagram showing the set point of the reactor water level according to an embodiment of the present invention, Fig. 2 is a diagram showing transient changes in each parameter of a conventional nuclear reactor, and Fig. 3 is a diagram showing the reactor water level set point according to an embodiment of the present invention. FIG. 2 is a diagram showing transient changes in each parameter of FIG. 1... Reactor pressure vessel, 4... Reactor water,
Ll, L2, L3, L4... Water level setting point.
Claims (1)
位の下限より低水位側に向つて、低水位アラームを指令
する第４の水位設定点と、原子炉スクラム信号を起生す
るとともに主蒸気隔離弁以外の隔離弁の閉鎖を指令する
第３の水位設定点と、主蒸気隔離弁の閉鎖、高圧炉心ス
プレイ系の起動ならびに原子炉隔離時冷却系の起動をそ
れぞれ指令する第２の水位設定点と、非常用炉心冷却系
の起動を指令する第１の水位設定点とを上記原子炉圧力
容器に上記の順序に設け、上記炉水位が上記第１乃至第
４の各設定点に到達したとき、上記第１乃至第４の各設
定点に対応する上記各安全保護手段を作動させる沸騰水
型原子炉の安全保護方法において、上記炉水位が、上記
第３の水位設定点まで低下したとき、上記主蒸気隔離弁
以外の隔離弁の閉鎖とあわせて、原子炉に設けられた再
循環ポンプの運転停止を指令することを特徴とする沸騰
水型原子炉の安全保護方法。 ２ 上記再循環ポンプの運転停止を、上記第３の水位設
定点が発生する信号と、主蒸気加減弁急閉指令信号との
論理積によつて行なう特許請求の範囲第１項記載の沸騰
水型原子炉の安全保護方法。[Claims] 1. A fourth water level set point for commanding a low water level alarm and a reactor scram signal toward a lower water level than the lower limit of the reactor water level in the reactor pressure vessel during normal reactor operation. a third water level set point that commands the closure of isolation valves other than the main steam isolation valve, the closure of the main steam isolation valve, the activation of the high pressure core spray system, and the activation of the reactor isolation cooling system. A second water level set point for commanding activation of the emergency core cooling system and a first water level set point for commanding activation of the emergency core cooling system are provided in the above order in the reactor pressure vessel, and the reactor water level is set at the first to fourth points. In the safety protection method for a boiling water reactor, in which the safety protection means corresponding to each of the first to fourth set points are activated when each set point is reached, the reactor water level is lower than the third water level. Safety protection for a boiling water reactor, characterized in that when the temperature drops to a set point, a command is given to shut down isolation valves other than the main steam isolation valve and to shut down a recirculation pump installed in the reactor. Method. 2. Boiling water according to claim 1, wherein the operation of the recirculation pump is stopped by the logical product of the signal for generating the third water level set point and the main steam control valve quick-closing command signal. Safety protection methods for type nuclear reactors.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP55017521A JPS6049278B2 (en) | 1980-02-15 | 1980-02-15 | Boiling water reactor safety protection method |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP55017521A JPS6049278B2 (en) | 1980-02-15 | 1980-02-15 | Boiling water reactor safety protection method |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS56114799A JPS56114799A (en) | 1981-09-09 |
| JPS6049278B2 true JPS6049278B2 (en) | 1985-10-31 |
Family
ID=11946249
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP55017521A Expired JPS6049278B2 (en) | 1980-02-15 | 1980-02-15 | Boiling water reactor safety protection method |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6049278B2 (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP6277466B2 (en) * | 2011-05-23 | 2018-02-14 | 元浩 岡田 | Nuclear power plant equipment. |
-
1980
- 1980-02-15 JP JP55017521A patent/JPS6049278B2/en not_active Expired
Also Published As
| Publication number | Publication date |
|---|---|
| JPS56114799A (en) | 1981-09-09 |
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