JPH0123076B2 - - Google Patents

Info

Publication number
JPH0123076B2
JPH0123076B2 JP56061292A JP6129281A JPH0123076B2 JP H0123076 B2 JPH0123076 B2 JP H0123076B2 JP 56061292 A JP56061292 A JP 56061292A JP 6129281 A JP6129281 A JP 6129281A JP H0123076 B2 JPH0123076 B2 JP H0123076B2
Authority
JP
Japan
Prior art keywords
steam
main steam
radioactivity
outflow
valve
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
Application number
JP56061292A
Other languages
Japanese (ja)
Other versions
JPS57175994A (en
Inventor
Tooru Sawayama
Takao Fujii
Hideo Kitagawa
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Mitsubishi Heavy Industries Ltd
Original Assignee
Mitsubishi Atomic Power Industries Inc
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Mitsubishi Atomic Power Industries Inc filed Critical Mitsubishi Atomic Power Industries Inc
Priority to JP56061292A priority Critical patent/JPS57175994A/en
Publication of JPS57175994A publication Critical patent/JPS57175994A/en
Publication of JPH0123076B2 publication Critical patent/JPH0123076B2/ja
Granted legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Measurement Of Radiation (AREA)

Description

【発明の詳細な説明】 本発明は、原子力発電設備、特に、加圧水型原
子力発電設備における主蒸気の大気放出時の放射
能監視装置に関するものである。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a radioactivity monitoring device for releasing main steam into the atmosphere in nuclear power generation equipment, particularly in pressurized water type nuclear power generation equipment.

加圧水型原子力発電設備における蒸気発生器の
細管の漏洩時に主蒸気管中の蒸気逃し弁や安全弁
が作動した場合には、主蒸気管中に含まれる放射
性物質が大気中に流出する。従つて、このような
設備には、放射能を検出するための装置を備え、
原子力発電設備から万一外部へ流出した放射能量
を正しく知り、これに基づいて、その対策処置を
立てることが重要である。
If the steam relief valve or safety valve in the main steam pipe is activated when a narrow tube of a steam generator in a pressurized water nuclear power generation facility leaks, radioactive materials contained in the main steam pipe will leak into the atmosphere. Therefore, such equipment must be equipped with a device for detecting radioactivity,
It is important to accurately know the amount of radioactivity that leaks out from nuclear power generation facilities and to take countermeasures based on this information.

従来、蒸気発生器の細管漏洩時に、主蒸気逃し
弁又は安全弁から蒸気が大気へ流出し、放射能が
大気中へ流出した場合、例えば、一次冷却材中の
放射能分析に基づいて流出した放射能量を求めて
いた。しかしながら、この方法では、各弁からの
流出した放射能量を求めるためには、一次冷却材
のサンプリング分析、蒸気発生器の漏洩率の算
出、各弁からの放出蒸気量の算出など多くの手順
を要し、時間が掛かる欠点があつた。
Conventionally, when a steam generator leaks in a capillary, steam leaks into the atmosphere from the main steam relief valve or safety valve, and radioactivity leaks into the atmosphere. For example, based on radioactivity analysis in the primary coolant, the leaked radiation I was looking for ability. However, with this method, in order to determine the amount of radioactivity leaked from each valve, many steps are required, including sampling analysis of the primary coolant, calculation of the leak rate of the steam generator, and calculation of the amount of steam released from each valve. It had the disadvantage of being time consuming.

そこで、本発明は、簡単な装置で、この放射能
量を正確に且つ迅速に算出することのできる主蒸
気大気放出時の放射能監視装置を得ることをその
目的とするものである。
SUMMARY OF THE INVENTION An object of the present invention is to provide a radioactivity monitoring device for releasing main steam into the atmosphere, which can accurately and quickly calculate the amount of radioactivity using a simple device.

本発明においては、この目的を達成するため
に、原子力発電設備における蒸気発生器から引出
される主蒸気管に取付けられている主蒸気逃し弁
及び主蒸気安全弁にそれぞれ弁動作検出器を附設
し、同じ主蒸気管に取付けられている主蒸気圧力
計からの信号と弁動作検出器からの信号を流出蒸
気量演算器に接続させ、更に、主蒸気管の管外壁
近傍に放射線検出器を設け、これと流出蒸気量演
算器とを放出放射能量演算器に接続して成ること
を特徴とするものである。
In the present invention, in order to achieve this objective, a valve operation detector is attached to each of the main steam relief valve and the main steam safety valve that are attached to the main steam pipe drawn out from the steam generator in nuclear power generation equipment, A signal from a main steam pressure gauge and a signal from a valve operation detector installed in the same main steam pipe are connected to an outflow steam amount calculator, and a radiation detector is further provided near the outer wall of the main steam pipe. This device is characterized in that this and an outflow vapor amount calculator are connected to a released radioactivity amount calculator.

以下、本発明をその1実施例を示す添附図面に
基づいて説明する。
DESCRIPTION OF THE PREFERRED EMBODIMENTS The present invention will be described below with reference to the accompanying drawings showing one embodiment thereof.

図に示すように、蒸気発生器1に含まれる一次
冷却材との熱交換によつて発生した蒸気は、主蒸
気管2を経て引出され、タービン(図示していな
い)へ送られる。主蒸気管2には、並列に配置さ
れた主蒸気圧力計4及び主蒸気逃し弁5並びに数
組の主蒸気安全弁6がこの順序に連結されてお
り、これらの弁5,6が動作した時には、これら
の弁5,6から蒸気が流出するが、若しも、万
一、蒸気発生器1中で細管漏洩が発生しておれ
ば、蒸気と一緒に放射性物質が弁5,6から大気
中に流出することとなる。この場合、主蒸気管2
中の放射性物質濃度は、主蒸気管2の外壁近傍
で、かつ、主蒸気圧力計4の前部に設けられた放
射線検出器6によつて測定され、また、主蒸気管
2に設けられた各主蒸気逃し弁5及び安全弁6に
は、弁の開閉を検知する弁動作検出器7を取付
け、これらを流出蒸気量演算器8に接続し、ま
た、これには、主蒸気逃し弁5の上流側に配置さ
れている主蒸気圧力計4も接続されている。更
に、放射線検出器3と流出蒸気量演算器8とは、
放出放射能量演算器9に接続されている。
As shown in the figure, steam generated by heat exchange with a primary coolant contained in a steam generator 1 is drawn out through a main steam pipe 2 and sent to a turbine (not shown). A main steam pressure gauge 4, a main steam relief valve 5, and several sets of main steam safety valves 6 are connected to the main steam pipe 2 in this order, and when these valves 5 and 6 operate, , steam flows out from these valves 5 and 6, but if by any chance a capillary leak occurs in the steam generator 1, radioactive materials will flow out from the valves 5 and 6 into the atmosphere together with the steam. This will result in leakage. In this case, main steam pipe 2
The concentration of radioactive substances in the main steam pipe 2 is measured by a radiation detector 6 installed near the outer wall of the main steam pipe 2 and in front of the main steam pressure gauge 4. A valve operation detector 7 is attached to each main steam relief valve 5 and safety valve 6 to detect the opening and closing of the valve, and these are connected to an outflow steam amount calculator 8. A main steam pressure gauge 4 located on the upstream side is also connected. Furthermore, the radiation detector 3 and the outflow vapor amount calculator 8 are as follows:
It is connected to the emitted radioactivity amount calculator 9.

このようにして、流出蒸気量演算器8は主蒸気
逃し弁5及び主蒸気安全弁6の開閉の動作状態を
弁動作検出器7によつて確認すると、主蒸気管2
内の蒸気圧力によつて、漏洩蒸気量を演算するこ
とができる。更に、流出蒸気量演算器8は、放出
放射能量演算器9に接続されているので、蒸気発
生器1の中において伝熱細管の漏洩等の生じた時
に外部へ流出した放射性物質量は、放射線検出器
3によつて検出された主蒸気中の放射能レベル
と、流出蒸気量演算器8によつて求められた流出
蒸気量とから、放出放射能量演算器9によつて容
易に求めることができる。
In this way, when the outflow steam amount calculator 8 confirms the opening and closing operating states of the main steam relief valve 5 and the main steam safety valve 6 using the valve operation detector 7, the outflow steam amount calculator 8 detects the main steam pipe 2.
The amount of leaked steam can be calculated based on the steam pressure inside. Furthermore, since the outflow steam amount calculator 8 is connected to the emitted radioactivity amount calculator 9, the amount of radioactive material that leaks outside when a heat transfer tube leaks or the like occurs in the steam generator 1 is calculated as radiation. From the radioactivity level in the main steam detected by the detector 3 and the amount of outflow steam determined by the outflow steam amount calculator 8, it can be easily determined by the emitted radioactivity amount calculator 9. can.

このように、本発明においては、例えば、100
万kW級の設備の場合、蒸気発生器1が4基設置
されているものとし、それぞれの蒸気発生器1か
ら発生した蒸気は、それぞれの主蒸気管2を介し
て導かれ、主蒸気ヘツダにおいて合流した後、タ
ービンへ送られるが、各主蒸気管2には、上記の
ように、主蒸気圧力計4、主蒸気逃し弁5、主蒸
気安全弁6等が設置されているものとすると、万
一、いずれかの蒸気発生器1中で伝熱細管の漏
洩、あるいは、破断が起つた時には、放射能を含
む原子炉冷却材が蒸気側(二次冷却系)へ漏れ込
み、蒸気中に放射性物質が混入することになり、
例えば、この時、原子力発電設備が外部から供給
されている電源が喪失した場合、その蒸気発生器
1に属する主蒸気管2に設けられている多くの主
蒸気逃し弁5及び安全弁6(この設例の場合に
は、総計8個)が動作し、主蒸気管2中の蒸気が
一時的に動作した弁5、6から大気中に流出する
こととなる。
In this way, in the present invention, for example, 100
In the case of a 10,000 kW class facility, it is assumed that four steam generators 1 are installed, and the steam generated from each steam generator 1 is led through each main steam pipe 2 and sent to the main steam header. After merging, the steam is sent to the turbine, but assuming that each main steam pipe 2 is equipped with a main steam pressure gauge 4, a main steam relief valve 5, a main steam safety valve 6, etc., as described above. 1. When a heat transfer tube leaks or breaks in any of the steam generators 1, the reactor coolant containing radioactivity leaks into the steam side (secondary cooling system), causing radioactivity in the steam. Substances may be mixed in,
For example, at this time, if the nuclear power generation equipment loses power supplied from outside, many main steam relief valves 5 and safety valves 6 installed in the main steam pipe 2 belonging to the steam generator 1 (in this example In this case, a total of 8 valves are operated, and the steam in the main steam pipe 2 flows out into the atmosphere from the temporarily operated valves 5 and 6.

従つて、放射線検出器3を主蒸気逃し弁5及び
安全弁6よりも上流の主蒸気管2の管外壁近傍に
取付け、伝熱細管漏洩時、主蒸気中に混入した放
射能による放射線を測定することによつて、主蒸
気管2の中に含まれる放射能レベルを知ることが
できる。
Therefore, a radiation detector 3 is installed near the outer wall of the main steam pipe 2 upstream of the main steam relief valve 5 and the safety valve 6 to measure the radiation caused by the radioactivity mixed into the main steam when the heat transfer tube leaks. By this, the level of radioactivity contained in the main steam pipe 2 can be known.

また、逃し弁5及び安全弁6から流出する蒸気
流量は、各弁5,6に附設された弁動作(開、
閉)検出器7の信号と、主蒸気管圧力計4の値と
から、これらの圧力計4及び検出器7に接続され
た放出蒸気量演算器8によつて求められ、放射線
検出器3及び放出蒸気量演算器8に接続されてい
る放出放射能量演算器9によつて全放出放射能量
が容易に求められる。
In addition, the flow rate of steam flowing out from the relief valve 5 and the safety valve 6 is determined by the valve operation (open, open, etc.) attached to each valve 5, 6.
From the signal of the closed) detector 7 and the value of the main steam pipe pressure gauge 4, the released steam amount calculator 8 connected to these pressure gauges 4 and detector 7 calculates the amount of steam released, and the radiation detector 3 and The total released radioactivity amount can be easily determined by the released radioactivity amount calculator 9 connected to the released steam amount calculator 8.

以上のように、本発明によると、原子力発電設
備、特に、加圧水型の原子力発電設備における蒸
気発生器の伝熱細管の漏洩時に、万一外部電源が
喪失した場合のように、主蒸気逃し弁、安全弁か
ら放射性物質を含む蒸気が流出した時に、流出し
た放射能量を容易に且つ連続して知ることができ
るので、本発明な原子力発電設備における安全対
策として、きわめて有効な装置を提供することが
できる。
As described above, according to the present invention, in the event of a leakage in the heat transfer tube of the steam generator in nuclear power generation equipment, particularly in pressurized water type nuclear power generation equipment, the main steam relief valve When steam containing radioactive materials flows out from a safety valve, the amount of radioactivity that has flowed out can be easily and continuously determined. Therefore, it is possible to provide an extremely effective device as a safety measure in nuclear power generation equipment according to the present invention. can.

【図面の簡単な説明】[Brief explanation of drawings]

図は、この発明による主蒸気大気放出時の放射
能監視装置を示す略図である。 1…蒸気発生器、2…主蒸気管、3…放射線検
出器、4…主蒸気圧力計、5…主蒸気逃し弁、6
…主蒸気安全弁、7…弁動作(開、閉)検出器、
8…流出蒸気量演算器、9…放出放射能量演算
器。
The figure is a schematic diagram showing a radioactivity monitoring device when main steam is released into the atmosphere according to the present invention. 1...Steam generator, 2...Main steam pipe, 3...Radiation detector, 4...Main steam pressure gauge, 5...Main steam relief valve, 6
...Main steam safety valve, 7...Valve operation (open, close) detector,
8...Outflow vapor amount calculator, 9...Release radioactivity amount calculator.

Claims (1)

【特許請求の範囲】[Claims] 1 原子力発電設備において、蒸気発生器から引
出される主蒸気管上に取付けられている主蒸気逃
し弁及び主蒸気安全弁にそれぞれ弁動作検出器を
附設し、同じく主蒸気管に取付けられている主蒸
気圧力計及び前記各弁動作検出器からの信号を入
力とし流出蒸気量を求める流出蒸気量演算器と、
主蒸気管の管外壁近傍に放射線検出器を取付け、
前記放射線検出器からの信号と、前記流出蒸気量
演算器からの信号を入力とし流出放射能量を求め
る放射能量演算器とにより構成したことを特徴と
する原子力発電設備における主蒸気大気放出時の
放射能監視装置。
1 In nuclear power generation facilities, a valve operation detector is attached to each of the main steam relief valve and main steam safety valve that are installed on the main steam pipe leading out from the steam generator, and the main steam safety valve that is also installed on the main steam pipe an outflow steam amount calculator that receives signals from the steam pressure gauge and each of the valve operation detectors and calculates the outflow steam amount;
A radiation detector is installed near the outer wall of the main steam pipe,
Radiation at the time of release of main steam into the atmosphere in a nuclear power generation facility, characterized in that it is constituted by a radioactivity amount calculator that receives a signal from the radiation detector and a signal from the outflow steam amount calculator and calculates the amount of outflow radioactivity. performance monitoring device.
JP56061292A 1981-04-24 1981-04-24 Radioactivity monitoring device at main steam release in atomic power plant Granted JPS57175994A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP56061292A JPS57175994A (en) 1981-04-24 1981-04-24 Radioactivity monitoring device at main steam release in atomic power plant

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP56061292A JPS57175994A (en) 1981-04-24 1981-04-24 Radioactivity monitoring device at main steam release in atomic power plant

Publications (2)

Publication Number Publication Date
JPS57175994A JPS57175994A (en) 1982-10-29
JPH0123076B2 true JPH0123076B2 (en) 1989-04-28

Family

ID=13166966

Family Applications (1)

Application Number Title Priority Date Filing Date
JP56061292A Granted JPS57175994A (en) 1981-04-24 1981-04-24 Radioactivity monitoring device at main steam release in atomic power plant

Country Status (1)

Country Link
JP (1) JPS57175994A (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP5456408B2 (en) * 2009-08-07 2014-03-26 三菱電機株式会社 Radioactive gas monitor

Also Published As

Publication number Publication date
JPS57175994A (en) 1982-10-29

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