JPH0132902B2 - - Google Patents
Info
- Publication number
- JPH0132902B2 JPH0132902B2 JP55014778A JP1477880A JPH0132902B2 JP H0132902 B2 JPH0132902 B2 JP H0132902B2 JP 55014778 A JP55014778 A JP 55014778A JP 1477880 A JP1477880 A JP 1477880A JP H0132902 B2 JPH0132902 B2 JP H0132902B2
- Authority
- JP
- Japan
- Prior art keywords
- signal
- predetermined value
- reactor
- exceeds
- radioactivity
- 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
- Ventilation (AREA)
- Air Conditioning Control Device (AREA)
Description
【発明の詳細な説明】
本発明は原子力発電所において、放射能放出事
故時に中央制御室(以下中操室と伝う)内に放射
性物質が直接流入することを防止するための中央
制御室換気空調系(以下中操換気系という)に関
するものである。Detailed Description of the Invention The present invention is a central control room ventilation air conditioning system for preventing radioactive materials from directly flowing into the central control room (hereinafter referred to as the "main control room") in the event of a radiation release accident in a nuclear power plant. system (hereinafter referred to as the central operation ventilation system).
原子力発電所において中操室は運転員が常駐
し、通常運転中はプラントの運転及び監視を行
い、事故時にはプラントに設けられている種々の
安全設備の機能の確認あるいは安全上の対策を行
うといつた原子力発電所の中枢機能を果たす場所
である。従つて、中操室はいかなる場合にも運転
員の適正な行動を妨げないような環境が維持され
なければならない。そのための対策の1つとし
て、中操室には中操換気系が設けられており、中
操室内の雰囲気温度あるいは湿度等を適切にコン
トロールすると同時に、通常時は、外気を一定割
合で導入し、中操室内の雰囲気を新鮮にし、運転
員が酸欠等を起こさないような設計が行なわれて
いる。ところが、放射性物質の放散を伴う原子炉
事故が起こつた場合には、中操換気系を隔離しな
いと放射性物質が中操室内に直接流入してしまい
運転員が放射線被曝を受け、場合によつては中操
室から運転員が退避する必要が生じてくる。この
ような事態を避けるため原子力発電所には従来、
想定事故の内炉心燃料に対する影響が最も厳しく
なる冷却材喪失事故時に中操室内に放射性物質が
直接流入することを防止できる中操換気系が設置
されている。 At a nuclear power plant, operators are permanently stationed in the central control room, and during normal operation they operate and monitor the plant, and in the event of an accident, they check the functionality of the various safety equipment installed in the plant or take safety measures. It is the place that performs the central functions of the Ituta Nuclear Power Plant. Therefore, an environment must be maintained in the central control room that does not interfere with the proper behavior of operators under any circumstances. As one measure to this end, the central operating room is equipped with a central operating room ventilation system, which appropriately controls the atmospheric temperature and humidity inside the central operating room, and at the same time, under normal conditions, outside air is introduced at a fixed rate. The design is such that the atmosphere inside the central control room is fresh and that operators do not suffer from oxygen deficiency. However, in the event of a nuclear reactor accident that involves the release of radioactive materials, if the central operating room ventilation system is not isolated, the radioactive materials will flow directly into the central operating room, causing operators to be exposed to radiation. In this case, it becomes necessary for operators to evacuate from the central control room. To avoid such situations, nuclear power plants have traditionally
A central operating room ventilation system has been installed to prevent radioactive materials from directly flowing into the central operating room in the event of a loss of coolant accident, which would have the most severe impact on the inner core fuel.
以下図面に基づいて中操換気系の従来例を説明
する。 A conventional example of a central operating ventilation system will be described below based on the drawings.
第1図に於いて原子炉が通常運転されている際
には中操室1内の雰囲気は再循環配管2を通り、
送風機3の吸引力により空調機4を通過して再び
中操室1にもどされる。空調機4は冷却器、加熱
器、フイルター等からなり、循環される雰囲気を
適温に維持すると同時に雰囲気中に浮遊する塵埃
を除去し雰囲気を浄化する機能を有している。一
方、外気取入口5からは一定量の外気が取り入れ
られ、隔離弁6を通過した後、循環している雰囲
気と合流し、送風機3の吸引力により空調機4を
通過して中操室1内に導入される。中操室1内の
雰囲気の一部は排風機7により排気口8から大気
中に放出される。この排気口8から放出される排
気風量と前記外気取入れ口5から導入される吸気
風量はバランスして等しくなる。このような状態
で中操換気系が運転されている際に原子炉の冷却
材喪失事故が発生すると、中操室1内に設置され
ている中操換気系隔離スイツチ9に事故信号が入
力され中操換気系隔離スイツチ9がONとなる。
これにより中操換気系隔離スイツチ9と電気的に
連結されている隔離弁6及び排風機7はそれぞれ
自動的に緊急閉鎖及び緊急停止される。 In Figure 1, when the reactor is in normal operation, the atmosphere inside the central operating room 1 passes through the recirculation pipe 2,
The suction force of the blower 3 causes the air to pass through the air conditioner 4 and return to the central operating room 1 again. The air conditioner 4 includes a cooler, a heater, a filter, etc., and has the function of maintaining the circulated atmosphere at an appropriate temperature and at the same time removing dust floating in the atmosphere to purify the atmosphere. On the other hand, a certain amount of outside air is taken in from the outside air intake port 5, passes through the isolation valve 6, merges with the circulating atmosphere, and is passed through the air conditioner 4 by the suction force of the blower 3 to the central control room. be introduced within. A part of the atmosphere in the central operating room 1 is discharged into the atmosphere from an exhaust port 8 by an exhaust fan 7. The amount of exhaust air discharged from the exhaust port 8 and the amount of intake air introduced from the outside air intake port 5 are balanced and equal. If a reactor loss of coolant accident occurs while the central operating room ventilation system is operating under these conditions, an accident signal will be input to the central operating room ventilation system isolation switch 9 installed in the central operating room 1. Central operation ventilation system isolation switch 9 is turned on.
As a result, the isolation valve 6 and the exhaust fan 7, which are electrically connected to the central operation ventilation system isolation switch 9, are automatically closed and stopped, respectively.
冷却材喪失事故が発生した場合に原子力発電所
内で検出され、中操換気系隔離スイツチに入力さ
れる事故信号を下記に示す。 When a loss of coolant accident occurs, the accident signal that is detected in the nuclear power plant and input to the central control ventilation system isolation switch is shown below.
1A 原子炉格納容器圧力高信号、 2A 原子炉水位低信号、 3A 原子炉建屋放射能高信号。1A Reactor containment vessel pressure high signal, 2A Reactor water level low signal, 3A Reactor building radioactivity high signal.
冷却材喪失事故は原子炉圧力容器に接続されてい
る配管が破断し、該原子炉圧力容器内に内蔵され
ている高温・高圧の冷却材が原子炉圧力容器を格
納している原子炉格能容器の中へ流出する事故で
ある。冷却材喪失事故時には高温・高圧の冷却材
が流出し急激に減圧沸謄を起こすため、原子炉格
納容器内の圧力が急上昇し、原子炉格納容器内に
設置された圧力計によつて原子炉格納容器圧力高
の事故信号が検出される。また、原子炉圧力容器
より冷却材が流出するため原子炉圧力容器中に設
置された水位計により原子炉水位低の事故信号が
検出される。さらに、原子炉圧力容器内に収納さ
れている炉心燃料からは放射性の核分裂生成物が
放出され、原子炉格納容器内に充満するが、この
核分裂生成物はごくわずかづつではあるが原子炉
格納容器の外部に漏洩する。その結果、原子炉格
納容器をさらに格納する形で設置されている原子
炉建屋内の放射線レベルが上昇する。原子炉建屋
内に設置されている放射線モニタがこの放射線レ
ベルの上昇を検知し、原子炉建屋内放射能高の事
故信号が検出される。これらの原子炉格納容器圧
力高、原子炉水位低及び原子炉建屋内放射能高の
事故信号はいずれも中操換気系隔離スイツチに入
力され、これらの事故信号のいずれかによつても
中操換気系隔離スイツチはONとなる。但し、プ
ラントの設計によつては原子炉建屋放射能高の事
故信号だけが中操換気系隔離スイツチに入力され
るようになつているものもある。このように原子
力発電所内で冷却材喪失事故が発生すると中操換
気系は必ず緊急隔離される設計となつており、核
分裂生成物が直接中操室内に流入することは防止
される。しかしながら原子力発電所では安全対策
上その発生を仮定する必要のある放射能放出事故
は前述の冷却材喪失事故だけとは限らず、それ以
外にも実に多くの事故が考えられる。それにもか
かわらず従来は冷却材喪失事故以外の放射能放出
事故時には中操換気系の自動隔離はいつさい行わ
れない設計になつており中操室内の運転員が不当
に放射線を被曝する恐れがあつた。A loss of coolant accident occurs when a pipe connected to a reactor pressure vessel ruptures, and the high-temperature, high-pressure coolant contained within the reactor pressure vessel causes damage to the reactor capacity that houses the reactor pressure vessel. This was an accident in which the liquid leaked into the container. In the event of a loss-of-coolant accident, high-temperature, high-pressure coolant flows out and rapidly depressurizes and boils, causing a sudden rise in pressure inside the reactor containment vessel, and pressure gauges installed inside the reactor containment vessel indicate that the reactor An accident signal of high containment vessel pressure is detected. In addition, since coolant flows out from the reactor pressure vessel, a water level gauge installed in the reactor pressure vessel detects an accident signal indicating a low reactor water level. Furthermore, radioactive fission products are released from the core fuel stored in the reactor pressure vessel and fill the reactor containment vessel, but these fission products are released outside the reactor containment vessel, albeit in very small amounts. leak. As a result, the radiation level inside the reactor building, which is installed to further contain the reactor containment vessel, increases. A radiation monitor installed inside the reactor building detects this increase in radiation level, and an accident signal of high radioactivity inside the reactor building is detected. These accident signals of high reactor containment vessel pressure, low reactor water level, and high radioactivity in the reactor building are all input to the central operating room ventilation system isolation switch. The ventilation system isolation switch is turned on. However, depending on the design of the plant, only the accident signal of high radioactivity in the reactor building is input to the central operation ventilation system isolation switch. In this way, when a loss of coolant accident occurs within a nuclear power plant, the central operating room ventilation system is always urgently isolated, and fission products are prevented from flowing directly into the central operating room. However, in nuclear power plants, the radioactivity release accident that must be assumed to occur for safety reasons is not limited to the aforementioned loss of coolant accident, but there are many other accidents that can be considered. Despite this, the conventional design has been such that automatic isolation of the central operating room ventilation system is not performed in the event of a radioactivity release accident other than a loss of coolant accident, and there is a risk that operators in the central operating room may be unduly exposed to radiation. It was hot.
本発明の目的は従来の中操換気系の欠点を改良
し、冷却材喪失事故以外の放射性物質の放散を伴
う原発事故が発生した場合にも、放射性物質が中
操室内に直接流入することを防止し得る中操換気
系を得ることにある。 The purpose of the present invention is to improve the shortcomings of conventional central operating room ventilation systems, and to prevent radioactive materials from directly flowing into the central operating room even in the event of a nuclear power plant accident involving the release of radioactive materials other than a loss of coolant accident. The objective is to obtain a central operation ventilation system that can prevent the above problems.
以下図面に基づいて本発明の一実施例を説明す
る。本発明は第2図に示すように外気取入れ口5
の近傍に放射線モニタ10を新設しこの放射線モ
ニターの電気信号を中操換気系隔離スイツチの入
力信号とする。本発明による中操換気系のその他
の部分の構成は従来の中操換気系と同様とする。
但し、中操換気系隔離スイツチに入力される事故
信号については原子力発電所で検出し得るものを
すべて入力信号とする。 An embodiment of the present invention will be described below based on the drawings. The present invention has an outside air intake 5 as shown in FIG.
A new radiation monitor 10 is installed near the radiation monitor, and the electrical signal from this radiation monitor is used as an input signal to the central operation ventilation system isolation switch. The configuration of other parts of the central operating ventilation system according to the present invention is the same as that of the conventional central operating ventilation system.
However, all accident signals that can be detected at the nuclear power plant shall be input to the central control ventilation system isolation switch.
また、同一敷地内に多数基の原子炉を設置する
場合には、どの原子炉の事故信号も残りすべての
原子炉の中換気系隔離スイツチの入力信号とす
る。 In addition, when multiple reactors are installed on the same site, the accident signal from any reactor is used as the input signal to the isolation switch for the internal ventilation system of all remaining reactors.
原子力発電所内で検出し得る中操換気系隔離ス
イツチの入力信号となる事故信号を下記に示す。 The accident signals that can be detected in a nuclear power plant and serve as input signals for the central control ventilation system isolation switch are shown below.
1A 原子炉格納器圧力高信号、
2A 原子炉水位低信号、
3A 原子炉建屋放射能高信号、
4A 主蒸気流量大信号、
5A 主蒸気トンネル温度高信号、
6A 主蒸気放射能高信号、
7A 冷却材浄化系差流量大信号、
8A 冷却材浄化系機器室温度高信号、
9A 残留熱除去系流量大信号、
10A 残留熱除去系機器室温度高信号、
11A タービン建屋エリア放射線モニタ放射能高
信号、
12A 廃棄物処理建屋エリア放射線モニタ放射能
高信号、
13A 排気筒モニタ放射能高信号。」
ここで以上の1A〜13Aの信号について説明す
る。なお、上記1Aから3Aの信号は従来例におい
て説明したので省略し、4A以下について説明す
る。1A Reactor containment pressure high signal, 2A Reactor water level low signal, 3A Reactor building radiation high signal, 4A Main steam flow rate large signal, 5A Main steam tunnel temperature high signal, 6A Main steam radiation high signal, 7A Cooling Material purification system differential flow rate large signal, 8A Coolant purification system equipment room temperature high signal, 9A Residual heat removal system flow rate large signal, 10A Residual heat removal system equipment room temperature high signal, 11A Turbine building area radiation monitor radioactivity high signal, 12A Waste treatment building area radiation monitor radioactivity high signal, 13A Exhaust stack monitor radioactivity high signal. ” Here, the above 1A to 13A signals will be explained. Note that the above-mentioned signals from 1A to 3A were explained in the conventional example, so they will be omitted, and the signals below 4A will be explained.
冷却材喪失事故は原子炉圧力容器に接続されて
いる配管が破断し、該原子炉圧力容器内に内蔵さ
れている高温・高圧の冷却材が原子炉圧力容器を
格納している原子炉格納容器等の系外へ流出する
事故である。この事故を検出するために上記1A
から10Aの信号がある。 A loss of coolant accident occurred when the piping connected to the reactor pressure vessel was ruptured, and the high-temperature, high-pressure coolant contained within the reactor pressure vessel was used to damage the reactor containment vessel that houses the reactor pressure vessel. This is an accident where the water leaks out of the system. 1A above to detect this accident
There is a 10A signal from.
まず主蒸気流量大信号4Aは、原子炉圧力容器
に接続された主蒸気配管内の主蒸気が漏洩し、主
蒸気の流量が所定値以上になつた場合に発信され
る信号である。そして、主蒸気トンネル温度高信
号5Aは、上述した様に主蒸気配管から主蒸気が
漏洩した場合、主蒸気配管を囲繞する主蒸気トン
ネル内に主蒸気が滞溜し、所定値以上になつた場
合に発信される信号である。前記主蒸気放射能高
信号6Aは、原子炉圧力容器内の水位が低下し燃
料の一部が破損し、燃料が冷却水中に拡散された
主蒸気内の放射能が所定値以上になつた場合に発
信される信号である。前記冷却材浄化系差流量大
信号7Aは、前記原子炉圧力容器に配管を介して
接続された冷却材浄化系の一部で洩漏事故が発生
し、冷却材浄化系の入口部における流量と出口部
における流量の差から求められる差流量が所定値
以上になつた場合に発信される信号である。前記
冷却材浄化系機器室温度高信号8Aは、前記冷却
材浄化系の一部を構成する機器(ポンプ等)が配
設される冷却材浄化系機器室内で冷却材浄化系か
ら漏洩が発生した場合、その漏洩蒸気によつて室
内の温度が所定値以上になる。この場合に発信さ
れる信号である。前記残留熱除去系流量大信号
9Aは、前記原子炉圧力容器に配管を介して接続
された残留熱除去系の一部で洩漏事故が発生し、
残留熱除去系の流量が所定値以上になつた場合に
発信される信号である。また、残留熱除去系機器
室温度高信号10Aは、前記残留熱除去系の一部を
構成する機器(ポンプ等)が配設される残留熱除
去機器室内で残留熱除去系から漏洩事故が発生
し、その漏洩蒸気によつて室内の温度が所定値以
上になつた場合に発信される信号である。 First, the main steam flow rate large signal 4A is a signal that is transmitted when main steam in the main steam piping connected to the reactor pressure vessel leaks and the flow rate of the main steam exceeds a predetermined value. The main steam tunnel temperature high signal 5A indicates that when main steam leaks from the main steam pipe as described above, the main steam accumulates in the main steam tunnel surrounding the main steam pipe and the temperature exceeds the predetermined value. This is the signal sent when The main steam radioactivity high signal 6A occurs when the water level in the reactor pressure vessel decreases, part of the fuel is damaged, and the radioactivity in the main steam where the fuel is diffused into the cooling water exceeds a predetermined value. This is a signal sent to The large differential flow rate signal 7A of the coolant purification system indicates that a leakage accident has occurred in a part of the coolant purification system connected to the reactor pressure vessel via piping, and the flow rate at the inlet and outlet of the coolant purification system are different. This is a signal that is sent when the differential flow rate calculated from the difference in flow rates at the two points exceeds a predetermined value. The high temperature signal 8A in the coolant purification system equipment room indicates that a leak has occurred from the coolant purification system in the coolant purification system equipment room where equipment (pumps, etc.) that constitute a part of the coolant purification system are installed. In this case, the indoor temperature rises to a predetermined value or higher due to the leaked steam. This is the signal sent in this case. The residual heat removal system flow rate large signal
9A, a leakage accident occurred in a part of the residual heat removal system connected to the reactor pressure vessel via piping.
This is a signal sent when the flow rate of the residual heat removal system exceeds a predetermined value. In addition, the residual heat removal system equipment room temperature high signal 10A indicates that a leakage accident occurred from the residual heat removal system in the residual heat removal equipment room where equipment (pumps, etc.) that constitute a part of the residual heat removal system is installed. However, this signal is sent when the indoor temperature rises to a predetermined value or higher due to the leaked steam.
さらに何らかの原因、例えば同一敷地内の他の
原子炉で事故が発生した場合等で原子炉建屋に側
設されたタービン建屋、廃棄物処理建屋、排気筒
において所定値以上の放射能が検出された場合に
はタービン建屋エリア放射線モニタ放射能高信号
11A、廃棄物処理建屋エリア放射線モニタ放射線
能高信号12A、排気筒モニタ放射能高信号13Aが
発信される。 Furthermore, due to some reason, such as an accident occurring at another nuclear reactor on the same site, radioactivity exceeding a specified value is detected in the turbine building, waste treatment building, or exhaust stack attached to the reactor building. Turbine building area radiation monitor in case of high radioactivity signal
11A, waste treatment building area radiation monitor high radiation activity signal 12A, and exhaust stack monitor high radiation activity signal 13A are transmitted.
次に本発明の作用を説明する。放射性物質の放
散を伴う原発事故が発生すると、風向によつては
放射性質が中操換気系の外気取入れ口5の近傍に
移動して来る。放射線モニタ10はこの放射性物
質の放射線を検知し、外気取入れ口放射能高の事
故信号を電気ケーブル11を介して中操換気系隔
離スイツチ9に入力する。これを受けて中操換気
系隔離スイツチ9はON状態となり、中操換気系
隔離スイツチ9と電気的に接続されている隔離弁
6及び排風機7はそれぞれ緊急閉鎖及び緊急停止
される。また、原子力発電所内の事故発生現場所
で直接事故信号が発生する場合にはその事故信号
が直接中操換気系隔離スイツチに入力され、その
後は上記と同様に中操換気系の隔離が行われる。 Next, the operation of the present invention will be explained. When a nuclear power plant accident involving the release of radioactive materials occurs, depending on the wind direction, the radioactive materials move to the vicinity of the outside air intake port 5 of the central operating ventilation system. The radiation monitor 10 detects the radiation of this radioactive substance and inputs an accident signal indicating the radioactivity level of the outside air intake port to the central operation ventilation system isolation switch 9 via the electric cable 11. In response to this, the central operating ventilation system isolation switch 9 is turned on, and the isolation valve 6 and exhaust fan 7, which are electrically connected to the central operating ventilation system isolation switch 9, are urgently closed and stopped, respectively. Additionally, if an accident signal is generated directly at the location of the accident in the nuclear power plant, the accident signal is directly input to the central operation ventilation system isolation switch, and thereafter the central operation ventilation system is isolated in the same way as above. .
上記のような作用を有する本発明の中操換気系
により以下の効果が得られる。原子力発電所内で
放射性物質の放散を伴う原発事故が発生した場合
でも、中操室内の放射線レベルは十分に低く抑え
られ、運転員の安全上重要な事故後対策活動が妨
げられるようなことはあつてはならない。そのた
めに従来、冷却材喪失事故が発生した場合には中
操換気系はただちに隔離され、外気としや断され
る設計となつている。しかしながら、原子力発電
所で安全対策上その発生を仮定する必要のある放
射能放出事故は冷却材喪失事故以外にも実に多く
のものがあり、これらが発生した場合には、中操
換気系は従来自動的に隔離されることはなく、中
操室内に放射性物質が直接流入してしまう恐れが
あつた。本発明による中操換気系は独自の放射線
モニタを有しているため、冷却材喪失事故はもと
より、それ以外の放射能放出事故が発生した場合
であつても、外気取入れ口放射能高の事故信号に
より隔離弁が自動閉鎖し、外気としや断され、放
射性物質が直接中操内に流入することが防止され
る効果が得られる。また、原子力発電所内の事故
発生場所で直接事故信号が発生する場合にはその
事故信号により直接中操換気系が隔離されるの
で、放射性物質が中操換気系の外気取入れ口の近
傍に到達する前に中操換気系を隔離することが可
能である。 The following effects can be obtained by the central ventilation system of the present invention having the above-mentioned functions. Even if a nuclear power plant accident occurs in a nuclear power plant that involves the release of radioactive materials, the radiation level in the central control room will be kept sufficiently low and will not interfere with post-accident countermeasures that are important for the safety of operators. must not. For this reason, conventional designs have been such that in the event of a loss of coolant accident, the central control ventilation system is immediately isolated and disconnected from outside air. However, there are many radioactivity release accidents other than coolant loss accidents that need to be assumed to occur for safety reasons at nuclear power plants, and when these occur, the central operating ventilation system is There was no automatic isolation, and there was a risk that radioactive materials could flow directly into the central control room. Since the central operating room ventilation system according to the present invention has its own radiation monitor, even if not only a coolant loss accident but also other radioactivity release accidents occur, an accident due to high radioactivity at the outside air intake will be detected. The isolation valve automatically closes in response to a signal, cutting off outside air and preventing radioactive materials from directly flowing into the central operating room. Additionally, if an accident signal is generated directly at the location of an accident within a nuclear power plant, the accident signal will directly isolate the central operation ventilation system, preventing radioactive materials from reaching the vicinity of the outside air intake of the central operation ventilation system. It is possible to isolate the central operating ventilation system before.
さらに、同一敷地内の他の原子炉で事故が発生
した場合にも、その原子炉側から送られてくる事
故信号により、中操換気系の隔離が可能である。
以上のように本発明による中操換気系によれば、
原子力発電所敷地内で発生するすべての放射能放
出事故に対し中操換気系はすみやかに外気としや
断され、放射性物質が内部に直接流入することが
防止されるので、運転員は不当な放射線被曝を受
けることなく事故後の対策を行うことが可能とな
る効果が得られる。 Furthermore, even if an accident occurs at another reactor on the same site, the central operating room ventilation system can be isolated based on the accident signal sent from that reactor.
As described above, according to the central operating ventilation system according to the present invention,
In the case of any radioactivity release accident that occurs on the premises of a nuclear power plant, the central operating ventilation system is immediately disconnected from the outside air, preventing radioactive materials from directly flowing into the interior, allowing operators to avoid undue radiation exposure. This has the effect of making it possible to take measures after an accident without being exposed to radiation.
第1図は従来の原子力発電所における中操換気
系の概略を示す系統図、第2図は本発明による中
操換気系の一実施例の概略を示す系統図である。
1……中央制御室(中操室)、2……再循環配
管、3……送風機、4……空調機、5……外気取
入れ口、6……隔離弁、7……排風機、8……排
気口、9……中央換気系隔離スイツチ、10……
放射線モニタ、11……電気ケーブル。
FIG. 1 is a system diagram schematically showing a central operating ventilation system in a conventional nuclear power plant, and FIG. 2 is a system diagram schematically showing an embodiment of a central operating ventilation system according to the present invention. 1... Central control room (center control room), 2... Recirculation piping, 3... Blower, 4... Air conditioner, 5... Outside air intake, 6... Isolation valve, 7... Exhaust fan, 8 ...Exhaust port, 9...Central ventilation system isolation switch, 10...
Radiation monitor, 11...electric cable.
Claims (1)
外気取入れ口から隔離弁を介して空気を取入れ、
排風機を介して排気口から前記中央制御室内の排
気を行なう中央制御室換気空調系において、前記
隔離弁及び排風機は、前記外気取入口の近傍に配
設された放射線モニタから所定量の放射線を検出
した場合に発信される外気取入れ口放射能高の事
故信号及び原子炉格納容器内の圧力が所定値以上
になつた場合に発信される原子炉格納容器圧力高
信号、前記原子炉格納容器内に配設された原子炉
圧力容器内の水位が所定値以下になつた場合に発
信される原子炉水位低信号、前記原子炉格納容器
を収容する原子炉建屋内の放射能が所定値以上に
なつた場合に発信される原子炉建屋放射能高信
号、前記原子炉圧力容器に接続された主蒸気配管
内を流れる主蒸気の流量が所定値以上になつた場
合に発信される主蒸気流量大信号、前記主蒸気配
管を囲繞する主蒸気トンネル内の温度が所定値以
上になつた場合に発信される主蒸気トンネル温度
高信号、前記主蒸気配管内を流れる主蒸気内の放
射線量が所定値以上になつた場合に発信される主
蒸気放射能高信号、前記原子炉圧力容器に配管を
介して接続された冷却材浄化系の入口流量と出口
流量の差から求められた差流量が所定値以上にな
つた場合に発信される冷却材浄化系差流量大信
号、前記冷却材浄化系の一部を構成する機器が配
設される冷却材浄化系機器室の温度が所定値以上
になつた場合に発信される冷却材浄化系機器室温
度高信号、前記原子炉圧力容器に配管を介して接
続された残留熱除去系内の流量が所定値以上にな
つた場合に発信される残留熱除去系流量大信号、
前記残留熱除去系の一部を構成する機器が配設さ
れる残留熱除去系機器室の温度が所定値以上にな
つた場合に発信される残留熱除去系機器室温度高
信号、前記原子炉建屋の側部に配置されたタービ
ン建屋内に配設される放射線モニタにて測定され
た値が所定値以上になつた場合に発信されるター
ビン建屋エリア放射線モニタ放射能高信号、前記
原子炉建屋の側部に配置された廃棄物処理建屋内
に配設される放射線モニタにて測定された値が所
定値以上になつた場合に発信される廃棄物処理建
屋エリア放射線モニタ放射能高信号、前記原子力
発電所内の排気を大気中に放出させる排気筒内の
放射能測定値が所定値以上になつた場合に発信さ
れる排気筒モニタ放射能高信号の内の一信号によ
つて閉動作及び停止して成ることを特徴とする中
央制御室換気空調系。1 Air is taken into the central control room located in the nuclear power plant from the outside air intake via the isolation valve,
In a central control room ventilation air conditioning system that exhausts air from the central control room from an exhaust port via an exhaust fan, the isolation valve and the exhaust fan collect a predetermined amount of radiation from a radiation monitor disposed near the outside air intake. an accident signal of high outdoor air intake radioactivity that is transmitted when a high radiation level is detected; a high pressure signal of the reactor containment vessel that is transmitted when the pressure inside the reactor containment vessel exceeds a predetermined value; The reactor water level low signal is sent when the water level in the reactor pressure vessel installed in the reactor pressure vessel falls below a predetermined value, and the radioactivity in the reactor building housing the reactor containment vessel exceeds a predetermined value. The reactor building radioactivity high signal is sent when the reactor building radioactivity is high, and the main steam flow rate is sent when the flow rate of main steam flowing in the main steam piping connected to the reactor pressure vessel exceeds a predetermined value. A large signal, a main steam tunnel temperature high signal that is sent when the temperature in the main steam tunnel surrounding the main steam pipe exceeds a predetermined value, and a radiation dose in the main steam flowing through the main steam pipe is a predetermined value. The main steam radioactivity high signal is transmitted when the radioactivity exceeds the specified value, and the differential flow rate determined from the difference between the inlet flow rate and outlet flow rate of the coolant purification system connected to the reactor pressure vessel via piping is a predetermined value. A coolant purification system difference flow rate large signal is sent when the temperature exceeds a predetermined value, and the temperature of the coolant purification system equipment room in which equipment forming part of the coolant purification system is installed exceeds a predetermined value. A high temperature signal in the coolant purification system equipment room is transmitted when the temperature in the equipment room of the coolant purification system is high, and a residual heat signal is transmitted when the flow rate in the residual heat removal system connected to the reactor pressure vessel via piping exceeds a predetermined value. Removal system flow rate large signal,
A residual heat removal system equipment room temperature high signal that is transmitted when the temperature of the residual heat removal system equipment room in which equipment constituting a part of the residual heat removal system is installed exceeds a predetermined value; Turbine building area radiation monitor radioactivity high signal transmitted when the value measured by the radiation monitor installed in the turbine building located on the side of the building exceeds a predetermined value, the reactor building A waste treatment building area radiation monitor radioactivity high signal that is transmitted when the value measured by a radiation monitor installed in the waste treatment building located on the side of the waste treatment building exceeds a predetermined value; Closes and stops in response to one of the exhaust stack monitor radioactivity high signals that are sent when the measured value of radioactivity in the stack, which releases exhaust gas from the nuclear power plant into the atmosphere, exceeds a predetermined value. A central control room ventilation air conditioning system characterized by comprising:
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1477880A JPS56113938A (en) | 1980-02-12 | 1980-02-12 | Air conditioning system for central control room |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1477880A JPS56113938A (en) | 1980-02-12 | 1980-02-12 | Air conditioning system for central control room |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS56113938A JPS56113938A (en) | 1981-09-08 |
| JPH0132902B2 true JPH0132902B2 (en) | 1989-07-11 |
Family
ID=11870503
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1477880A Granted JPS56113938A (en) | 1980-02-12 | 1980-02-12 | Air conditioning system for central control room |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS56113938A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2011027308A (en) * | 2009-07-24 | 2011-02-10 | Hitachi-Ge Nuclear Energy Ltd | Ventilation method of central control room and central control room ventilation device |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS4942139A (en) * | 1972-08-30 | 1974-04-20 |
-
1980
- 1980-02-12 JP JP1477880A patent/JPS56113938A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS56113938A (en) | 1981-09-08 |
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