JPS6345079B2 - - Google Patents
Info
- Publication number
- JPS6345079B2 JPS6345079B2 JP55159313A JP15931380A JPS6345079B2 JP S6345079 B2 JPS6345079 B2 JP S6345079B2 JP 55159313 A JP55159313 A JP 55159313A JP 15931380 A JP15931380 A JP 15931380A JP S6345079 B2 JPS6345079 B2 JP S6345079B2
- Authority
- JP
- Japan
- Prior art keywords
- water level
- pressure vessel
- signal
- differential pressure
- value
- 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
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 67
- 239000007788 liquid Substances 0.000 claims description 20
- 238000009835 boiling Methods 0.000 claims description 17
- 230000005856 abnormality Effects 0.000 claims description 15
- 230000002159 abnormal effect Effects 0.000 claims description 10
- 230000005494 condensation Effects 0.000 claims description 7
- 238000009833 condensation Methods 0.000 claims description 7
- 238000001514 detection method Methods 0.000 claims description 7
- 239000012071 phase Substances 0.000 claims 2
- 239000007791 liquid phase Substances 0.000 claims 1
- 238000010586 diagram Methods 0.000 description 2
- 230000007423 decrease Effects 0.000 description 1
- 230000007257 malfunction Effects 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
- G21C17/022—Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
-
- 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
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Measurement Of Levels Of Liquids Or Fluent Solid Materials (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【発明の詳細な説明】
本発明は、沸騰水形原子炉の原子炉圧力容器に
配設される差圧式水位計の異常検出装置に関す
る。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to an abnormality detection device for a differential pressure water level gauge installed in a reactor pressure vessel of a boiling water nuclear reactor.
一般に沸騰水形原子炉では、差圧式水位計を用
いて、原子炉圧力容器内の水位を測定することが
行なわれている。 Generally, in boiling water nuclear reactors, a differential pressure type water level gauge is used to measure the water level in the reactor pressure vessel.
第１図は、沸騰水形原子炉の原子炉圧力容器１
に配設された凝縮槽型差圧式水位計を示してお
り、原子炉圧力容器１の上部側方には、一端を原
子炉圧力容器１の気相部２に開口する導圧管３の
他端に接続され、基準液面４を形成する凝縮槽５
が配置されている。 Figure 1 shows reactor pressure vessel 1 of a boiling water reactor.
The figure shows a condensing tank type differential pressure water level gauge installed in the reactor pressure vessel 1, and on the upper side of the reactor pressure vessel 1, the other end of a pressure impulse pipe 3 whose one end opens into the gas phase part 2 of the reactor pressure vessel 1 is shown. A condensing tank 5 connected to the water and forming a reference liquid level 4
is located.
また、原子炉圧力容器１の下部側方には、差圧
測定器６が配置されており、この差圧測定器６に
は、原子炉圧力容器１の液面下に開口する導圧管
７および凝縮槽５に開口する導圧管８が接続され
ている。 Further, a differential pressure measuring device 6 is arranged at the lower side of the reactor pressure vessel 1, and this differential pressure measuring device 6 includes a pressure impulse pipe 7 and a A pressure impulse pipe 8 opening into the condensing tank 5 is connected.
この差圧測定器６は、導圧管７および８の差圧
測定器６への接続部における差圧を測定する。 This differential pressure measuring device 6 measures the differential pressure at the connection of the impulse lines 7 and 8 to the differential pressure measuring device 6.
なお、９は水位算出器であり、差圧測定器６で
測定された差圧に基づいて、原子炉圧力容器１の
水位を算出する。 Note that 9 is a water level calculator, which calculates the water level in the reactor pressure vessel 1 based on the differential pressure measured by the differential pressure measuring device 6.
また、１０は炉心を示している。 Further, 10 indicates the reactor core.
このように構成された凝縮槽型差圧式水位計で
は、原子炉圧力容器１の水位は以下述べるように
して測定される。 In the condensing tank type differential pressure water level gauge configured as described above, the water level in the reactor pressure vessel 1 is measured as described below.
すなわち、例えば差圧測定器６の高さ位置を基
準水位（水位０ｍ）とし、そこから、原子炉圧力
容器１の液面下に開口する導圧管７の開口部まで
の高さ円H1ｍ、凝縮槽５の基準液面４での高さ
をH0ｍとし、また、原子炉圧力容器１内の蒸気
の平均比重量をγvKg／m3、水の平均比重量をγL
Kg／m3、凝縮槽５内の液体の平均比重量をγc
Kg／m3とし、差圧測定器６による差圧の測定値が
△ＰKg／m2であつたとすると、一般に原子炉圧力
容器１の水位Ｈは次式で求めることができる。 That is, for example, let the height position of the differential pressure measuring device 6 be the reference water level (water level 0 m), and the height circle H 1 m from there to the opening of the impulse pipe 7 that opens below the liquid level of the reactor pressure vessel 1. , the height of the condensing tank 5 at the reference liquid level 4 is H 0 m, the average specific weight of steam in the reactor pressure vessel 1 is γvKg/m 3 , and the average specific weight of water is γL
Kg/m 3 , the average specific weight of the liquid in the condensing tank 5 is γc
Kg/m 3 and the differential pressure measured by the differential pressure measuring device 6 is ΔPKg/m 2 , the water level H in the reactor pressure vessel 1 can generally be determined by the following equation.
Ｈ＝Ho（γc−γv）−△Ｐ／γL−γv ………(A)
しかしながら、実際には、通常Hoはほぼ一定
であり、また、γc、γv、γLの値も定格運転時の
値を固定して使用しているため、水位計算出器９
では、差圧測定器６の測定値が△Ｐである場合に
は、次式を用いて水位Ｈを求めている。 H=Ho(γc−γv)−△P/γL−γv……(A) However, in reality, usually Ho is almost constant, and the values of γc, γv, and γL are also the values at rated operation. Since the water level calculator 9 is used as a fixed
In this case, when the measured value of the differential pressure measuring device 6 is ΔP, the water level H is determined using the following equation.
Ｈ＝α−△Ｐ／β ………(B) ここで、αおよびβは定数であり、 α≡Ho（γc−γv）、β≡γL−γvである。 H=α−△P/β……(B) Here, α and β are constants, α≡Ho(γc−γv), β≡γL−γv.
しかしながら、このように構成された差圧式水
位計では、原子炉圧力容器１内の蒸気圧力が急激
に減少したり、また、凝縮槽５内の温度が急激に
上昇したりしたときには、凝縮槽５内の液体が沸
騰し、液体の平均比重量γcが大幅に変化する。 However, in the differential pressure type water level gauge configured in this way, when the steam pressure in the reactor pressure vessel 1 suddenly decreases or the temperature in the condensing tank 5 suddenly increases, the condensing tank 5 The liquid inside boils, and the average specific weight γc of the liquid changes significantly.
また、凝縮槽５内の液体の沸騰が急激な場合に
は、凝縮槽５内の一部の液体が原子炉圧力容器１
内へ流出し基準液面４の高さHoが変化すること
になる。 In addition, if the liquid in the condensing tank 5 boils rapidly, some of the liquid in the condensing tank 5 will be transferred to the reactor pressure vessel.
As a result, the height Ho of the reference liquid level 4 changes.
このような場合には、実際には、γcやHoが変
化しているにもかかわらず、水位算出器９は、あ
らかじめ測定された値に基づいて定数αおよびβ
が決められた前記(B)式を用いて水位Ｈを求めるた
め、この水位算出器９により求められた水位Ｈ
は、実際の値とはかけ離れたものとなつている。 In such a case, even though γc and Ho are changing, the water level calculator 9 calculates the constants α and β based on the previously measured values.
Since the water level H is determined using the formula (B) in which
is far from the actual value.
また、このように構成された差圧式水位計で
は、本来、原子炉圧力容器１への導圧管７の開口
部より低い水位Ｈおよび凝縮槽５の基準液面４よ
り高い水位Ｈを測定することはできないが、差圧
測定器６や水位算出器９の故障等により、水位算
出器９による計算値がこれらの範囲を越えてしま
うことがある。 In addition, the differential pressure type water level gauge configured in this manner originally measures a water level H lower than the opening of the impulse pipe 7 to the reactor pressure vessel 1 and a water level H higher than the reference liquid level 4 of the condensation tank 5. However, due to a failure of the differential pressure measuring device 6 or the water level calculating device 9, the value calculated by the water level calculating device 9 may exceed these ranges.
以上述べたような原因により、差圧式水位計の
水位指示値が実際には誤つているにもかかわらず
原子炉の運転を続ける場合には、原子炉の緊急停
止ひいては、炉心１０の露出事故に至る危険性が
ある。 Due to the causes mentioned above, if the reactor continues to operate even though the water level indication value of the differential pressure type water level gauge is actually incorrect, it may lead to an emergency shutdown of the reactor and an accident of exposure of the reactor core 10. There is a danger of this happening.
本発明は、かかる事情に対処してなされたもの
で、凝縮槽５内で液体が沸騰したり、また差圧測
定器６または水位算出器９が故障している等の理
由により、差圧式水位計の指示値に誤まりがある
ときに、異常信号を出力する沸騰水形原子炉圧力
容器水位計の異常検出装置を提供しようとするも
のである。 The present invention has been made in response to such circumstances, and due to reasons such as boiling of liquid in the condensing tank 5 or failure of the differential pressure measuring device 6 or the water level calculator 9, etc., the differential pressure type water level An object of the present invention is to provide an abnormality detection device for a boiling water reactor pressure vessel water level gauge that outputs an abnormality signal when there is an error in the indicated value of the gauge.
以下、本発明の詳細を第２図に示す一実施例に
ついて説明する。なお、第２図において第１図と
共通する部分は同一符号で示している。 Hereinafter, details of the present invention will be explained with reference to an embodiment shown in FIG. Note that in FIG. 2, parts common to those in FIG. 1 are indicated by the same reference numerals.
第２図に示す沸騰水形原子炉圧力容器水位計の
異常検出装置１１は、圧力信号入力部Ａ、温度信
号入力部Ｂ、水位信号入力部Ｃ、異常判断部Ｄ、
異常信号出力部Ｅとから構成されている。 The abnormality detection device 11 of the boiling water reactor pressure vessel water level gauge shown in FIG. 2 includes a pressure signal input section A, a temperature signal input section B, a water level signal input section C, an abnormality determination section D,
It consists of an abnormal signal output section E.
圧力信号入力部Ａは、原子炉圧力容器１上部の
蒸気圧を測定する蒸気圧力検出器１２からの圧力
信号ａを入力する。 The pressure signal input section A inputs the pressure signal a from the steam pressure detector 12 that measures the steam pressure in the upper part of the reactor pressure vessel 1.
なお、蒸気圧力検出器１２は、すでに一般の沸
騰水形原子炉には配置されているので、これを用
いるのが望ましい。 Incidentally, since the steam pressure detector 12 is already installed in a general boiling water reactor, it is desirable to use this.
温度信号入力部Ｂは、凝縮槽５内の液体の温度
を測定する温度検出器１３からの温度信号ｂを入
力する。なお、温度検出器１３は、この装置を使
用するために別途設けられたものである。 The temperature signal input section B inputs the temperature signal b from the temperature detector 13 that measures the temperature of the liquid in the condensation tank 5. Note that the temperature detector 13 is separately provided in order to use this device.
水位信号入力部Ｃは、水位算出器９で算出され
た水位信号ｃを入力する。 The water level signal input section C inputs the water level signal c calculated by the water level calculator 9.
異常判断部Ｄは、圧力信号入力部Ａに入力され
た圧力信号ａに基づいて、凝縮槽５内の液体１４
の沸点Tfを算出するとともに、この算出された
値と、温度信号入力部Ｂに入力された温度信号ｂ
の値とを比較して、温度信号ｂの値が沸点Tfよ
り大きい場合には、凝縮槽５内で液体１４が沸騰
しているとして、異常信号を次に述べる異常信号
出力部Ｅへ出力する。 The abnormality determination section D determines whether the liquid 14 in the condensing tank 5 is determined based on the pressure signal a input to the pressure signal input section A.
The boiling point Tf of is calculated, and this calculated value and the temperature signal b input to the temperature signal input section B are
When the value of the temperature signal b is larger than the boiling point Tf, it is determined that the liquid 14 is boiling in the condensing tank 5, and an abnormal signal is output to the abnormal signal output section E described below. .
また、水位信号入力部Ｃに入力された水位信号
ｃを常時または、周期的に監視し、水位信号ｃの
値が、原子炉圧力容器１への導圧管７の開口部よ
り低い水位Ｈおよび凝縮槽５の基準液面４より高
い水位Ｈを示している場合には、差圧測定器６ま
たは水位算出器９が故障しているとして、異常信
号を異常信号出力部Ｅへ出力する。 In addition, the water level signal c input to the water level signal input section C is constantly or periodically monitored, and the water level H and condensation are determined when the value of the water level signal c is lower than the opening of the impulse pipe 7 to the reactor pressure vessel 1. If the water level H is higher than the reference liquid level 4 of the tank 5, it is assumed that the differential pressure measuring device 6 or the water level calculating device 9 is out of order, and an abnormal signal is output to the abnormal signal output section E.
異常信号出力部Ｅは、異常判断部Ｄから異常信
号が入力された時には、この異常信号を例えば、
中央制御室の警報装置（図示せず）に出力する。 When an abnormal signal is input from the abnormality determining section D, the abnormal signal output section E outputs this abnormal signal to, for example,
Output to an alarm device (not shown) in the central control room.
以上述べたように本発明の沸騰水形原子炉圧力
容器水位計の異常検出装置によれば、凝縮槽５内
で液体１４が沸騰していたり、また差圧測定器６
または水位算出器９が故障している時の理由によ
り、差圧式水位計の指示値に誤まりがある場合に
は、異常信号が出力され、運転員に警報が発せら
れるので、原子炉の安全性をさらに高めることが
できる。 As described above, according to the abnormality detection device for a boiling water reactor pressure vessel water level gauge of the present invention, if the liquid 14 is boiling in the condensing tank 5 or the differential pressure measuring device 6
Or, if there is an error in the indicated value of the differential pressure type water level gauge due to a malfunction of the water level calculator 9, an abnormality signal is output and a warning is issued to the operators, ensuring the safety of the reactor. You can further enhance your sexuality.
なお、実施例においては、凝縮槽型差圧式水位
計に本発明を適用した例について説明したが、本
発明はかかる差圧式水位計に限定されるものでは
なく、例えば恒温槽型差圧式水位計のような差圧
式水位計にも適用できることは勿論である。 In addition, in the embodiment, an example in which the present invention is applied to a condensing tank type differential pressure type water level gauge is explained, but the present invention is not limited to such a differential pressure type water level gauge. Of course, it can also be applied to differential pressure type water level gauges such as.
第１図は、凝縮槽型差圧式水位計の説明図、第
２図は、本発明の沸騰水形原子炉圧力容器水位計
の異常検出装置の一実施例を示すブロツク線図で
ある。
１……原子炉圧力容器、５……凝縮槽、６……
差圧測定器、９……水位算出器、１１……異常検
出装置、Ａ……圧力信号入力部、Ｂ……温度信号
入力部、Ｃ……水位信号入力部、Ｄ……異常判断
部、Ｅ……異常信号出力部、ａ……圧力信号、ｂ
……温度信号、ｃ……水位信号。
FIG. 1 is an explanatory diagram of a condensing tank type differential pressure water level gauge, and FIG. 2 is a block diagram showing an embodiment of an abnormality detection device for a boiling water reactor pressure vessel water level gauge according to the present invention. 1... Reactor pressure vessel, 5... Condensation tank, 6...
Differential pressure measuring device, 9... Water level calculator, 11... Abnormality detection device, A... Pressure signal input section, B... Temperature signal input section, C... Water level signal input section, D... Abnormality determination section, E... Abnormal signal output section, a... Pressure signal, b
...Temperature signal, c...Water level signal.
Claims (1)
に連通されて、基準液面を形成する凝縮槽と、第
２の導圧管により前記凝縮槽に連通され、第３の
導圧管により原子炉圧力容器の液相部と連通され
た差圧測定器と、この差圧測定器で測定された差
圧に基づいて前記原子炉圧力容器の水位を算出す
る水位算出器とを備えた差圧式水位計の異常を検
出する装置において、前記原子炉圧力容器気相部
の蒸気圧を測定する蒸気圧力検出器からの圧力信
号、前記凝縮槽内に収容された液体の温度を検出
する温度検出器からの温度信号および前記水位算
出器で算出された水位信号をそれぞれ入力する入
力部と、前記入力部に入力された圧力信号に基づ
いて、前記凝縮槽内の前記液体の沸点の値を算出
し、この算出された沸点の値と前記入力部に入力
された温度信号の値とを比較して、この温度信号
の値が前記沸点の値より大きいとき、および前記
入力部に入力された水位信号の値が前記原子炉圧
力容器への第３の導圧管の開口部の高さより低い
値を示しているとき、または、前記凝縮槽の基準
液面より高い値を示している場合に異常信号を出
力する異常判断部を備えてなることを特徴とする
沸騰水形原子炉圧力容器水位計の異常検出装置。1 A condensation tank that is connected to the gas phase part of the reactor pressure vessel by a first impulse line to form a reference liquid level; A differential pressure type comprising a differential pressure measuring device communicating with the liquid phase part of the reactor pressure vessel, and a water level calculator that calculates the water level of the reactor pressure vessel based on the differential pressure measured by the differential pressure measuring device. In a device for detecting an abnormality in a water level gauge, a pressure signal from a steam pressure detector that measures the steam pressure in the gas phase portion of the reactor pressure vessel, and a temperature detector that detects the temperature of the liquid contained in the condensation tank. and an input section into which a temperature signal from the water level calculator and a water level signal calculated by the water level calculator are respectively input, and a value of the boiling point of the liquid in the condensing tank is calculated based on the pressure signal input to the input section. , the calculated boiling point value is compared with the value of the temperature signal input to the input section, and when the value of this temperature signal is greater than the boiling point value, and the water level signal input to the input section An abnormal signal is generated when the value of is lower than the height of the opening of the third impulse pipe to the reactor pressure vessel, or higher than the reference liquid level of the condensation tank. An abnormality detection device for a boiling water reactor pressure vessel water level gauge, comprising an abnormality determination section that outputs an output.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP55159313A JPS5782718A (en) | 1980-11-12 | 1980-11-12 | Fault detector for water gauge of pressure container of boiling water type nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP55159313A JPS5782718A (en) | 1980-11-12 | 1980-11-12 | Fault detector for water gauge of pressure container of boiling water type nuclear reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5782718A JPS5782718A (en) | 1982-05-24 |
| JPS6345079B2 true JPS6345079B2 (en) | 1988-09-07 |
Family
ID=15691063
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP55159313A Granted JPS5782718A (en) | 1980-11-12 | 1980-11-12 | Fault detector for water gauge of pressure container of boiling water type nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5782718A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106652360A (en) * | 2017-01-24 | 2017-05-10 | 深圳双创科技发展有限公司 | Robot-public security moving station participated alarm system and method |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS59137823A (en) * | 1983-01-28 | 1984-08-08 | Mitsubishi Heavy Ind Ltd | Measuring device for water level in container |
-
1980
- 1980-11-12 JP JP55159313A patent/JPS5782718A/en active Granted
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106652360A (en) * | 2017-01-24 | 2017-05-10 | 深圳双创科技发展有限公司 | Robot-public security moving station participated alarm system and method |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5782718A (en) | 1982-05-24 |
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