JPS59104593A - Water level measuring device in pressure vessel of bwr type reactor - Google Patents
Water level measuring device in pressure vessel of bwr type reactorInfo
- Publication number
- JPS59104593A JPS59104593A JP57213383A JP21338382A JPS59104593A JP S59104593 A JPS59104593 A JP S59104593A JP 57213383 A JP57213383 A JP 57213383A JP 21338382 A JP21338382 A JP 21338382A JP S59104593 A JPS59104593 A JP S59104593A
- Authority
- JP
- Japan
- Prior art keywords
- measuring device
- water level
- reactor
- pressure vessel
- neutron flux
- 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.)
- Pending
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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
〔発明の技術分野〕
本発明は、沸騰水型原子炉の原子炉圧力容器内の水位を
監視する水位ｄ１側装置の改良に関する。DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to an improvement of a water level d1 side device for monitoring the water level in a reactor pressure vessel of a boiling water nuclear reactor.
まず、従来の原子炉圧力容器内の水位計測装置を第１図
により説明する。First, a conventional water level measuring device in a nuclear reactor pressure vessel will be explained with reference to FIG.
原子炉圧力容器１の上部の蒸気ドーム２には連通管３が
接続されており、この４ ’Ｊ５Ｓ、 ’Ｗｌ ３の先
）ｆ：；＾には蒸気凝縮槽４が配設されている。また、
この蒸気凝縮槽４の下側には上下方向に延在する下部圧
力検出管５が接続されている。一方、７１子炉圧力容器
１の上下方向中間位１４には下部圧力検出管６が接続さ
れており、これらの両検出・け５，６に接続された差圧
測定器７によ９両検出管５，６の水柱差を測定して原子
炉圧力容器１内の水位を測定するようになっている。そ
して、この差圧測定器７の出力信号は圧力容器水位指示
器８および圧力容器水位設定器９に入力される。A communication pipe 3 is connected to the steam dome 2 at the upper part of the reactor pressure vessel 1, and a steam condensing tank 4 is disposed beyond this 4'J5S,'Wl3)f:;^. Also,
A lower pressure detection tube 5 extending in the vertical direction is connected to the lower side of the steam condensing tank 4. On the other hand, a lower pressure detection tube 6 is connected to the vertically intermediate position 14 of the 71 child reactor pressure vessel 1, and a differential pressure measuring device 7 connected to both of these detectors 5 and 6 detects the 9 pressure vessels. The water level in the reactor pressure vessel 1 is measured by measuring the water column difference between the pipes 5 and 6. The output signal of this differential pressure measuring device 7 is inputted to a pressure vessel water level indicator 8 and a pressure vessel water level setting device 9.
ところで、原子炉の運転中および過渡変化時において、
上記圧力容器１の上部の蒸気ドーム２内に圧力変動があ
ると、その圧力変動は上記上部および上部圧力検出管５
，６を通じて差圧測爺器７に伝達される。前記上部およ
び下部検出管５，６はその配管長および配管構成の相違
により、差圧測定器７に圧力変動を伝達する速度が異な
るため、差圧測定器７の出力信号は脈動現象を示す。こ
の出力信号は原子炉水位設定器９に入力されており、し
たがって前記の変動は、予期しないスクラム等の安全保
護動作をさせることもあり好ましくない。By the way, during nuclear reactor operation and during transient changes,
When there is a pressure fluctuation in the steam dome 2 at the upper part of the pressure vessel 1, the pressure fluctuation is detected by the upper and upper pressure detection tubes 5.
, 6 to the differential pressure meter 7. Because the upper and lower detection tubes 5 and 6 transmit pressure fluctuations to the differential pressure measuring device 7 at different speeds due to differences in their piping lengths and piping configurations, the output signal of the differential pressure measuring device 7 exhibits a pulsating phenomenon. This output signal is input to the reactor water level setting device 9, and therefore, the above-mentioned fluctuation is undesirable because it may cause an unexpected safety protection operation such as a scram.
本発明は、前述した従来のものにおける欠点を除去し、
正確でかつ安定した原子炉圧力容器内の水位を計測する
ことのできる沸騰水型原子炉の原子炉圧力容器内の水位
計測装置を提供することを目的とする。The present invention eliminates the drawbacks of the conventional ones mentioned above,
An object of the present invention is to provide a water level measuring device in a reactor pressure vessel of a boiling water reactor that can accurately and stably measure the water level in the reactor pressure vessel.
前述した目的は、本発明によれば、原子炉の出力を測定
する中性子束測定器と、差圧測定器および中性子束測定
器の出力信号が入力され、この中性子束測定器の出力信
号により差圧測定器の出力信号を補正、演算する水位補
正演算装置とを有することによシ達成される。According to the present invention, the output signals of a neutron flux measuring device that measures the output of a nuclear reactor, a differential pressure measuring device, and a neutron flux measuring device are input, and the output signals of the neutron flux measuring device measure the difference. This is achieved by having a water level correction calculation device that corrects and calculates the output signal of the pressure measuring device.
以下、本発明を図面に示す実施例により説明する。なお
前述した従来のものと同一のＦ１ｑ成については、図面
中に同一符号を付し、その説明は省略する。The present invention will be explained below with reference to embodiments shown in the drawings. Note that the F1q configurations that are the same as those of the prior art described above are designated by the same reference numerals in the drawings, and their explanations will be omitted.
第２図は本発明の実施例を示すものであり、差圧測定器
７の出力信号は水位補正演舞、装置ｉｏに入力され、こ
の水位補正、演算装置ＩＯの出力信号が圧力容器水位指
示器８および圧力容器水位設定器９に入力されるように
なっている。FIG. 2 shows an embodiment of the present invention, in which the output signal of the differential pressure measuring device 7 is input to the water level correction device IO, and the output signal of the water level correction device IO is input to the pressure vessel water level indicator. 8 and a pressure vessel water level setting device 9.
一方、原子炉圧力容器１内の炉心部に装架される燃料集
合体１１内には中性子束検出器】２が配設されており、
この中性子束検出’ｇ４１２の出方信号は中性子束測定
器１３に人力され、増幅、演算処理が行なわれる１、そ
して、この中性子束測定器１３の出方信号が前記水位補
正演算装置１０に入力され、前記差圧測定器７からの水
位信号は補正、演算される。On the other hand, a neutron flux detector]2 is installed in the fuel assembly 11 installed in the core of the reactor pressure vessel 1.
The output signal of this neutron flux detection 'g412 is input to the neutron flux measuring device 13, where it is amplified and arithmetic processed. Then, the water level signal from the differential pressure measuring device 7 is corrected and calculated.
つぎに、前述した実施列の作用について説明する。Next, the effect of the above-mentioned implementation sequence will be explained.
第３図ないし第５図は原子炉圧力容器ｌ内の蒸気ドーム
２の圧力Ｋ ＃Ｔｂ ＋呼における本発明の水位計測装
置の各個所の出力信号の時間的変化を示しだグラフであ
る。3 to 5 are graphs showing temporal changes in output signals at various points of the water level measuring device of the present invention at the pressure K #Tb + of the steam dome 2 in the reactor pressure vessel l.
このうち第３図は差圧測定器７０出方信号の変化を示す
グラフでオシ、原子炉圧カ谷器１内の蒸気ドーム２に圧
力変動が生じると、前述したように、上部および下部圧
力検出管５，６の長さおよび配管構成の相違によシ差圧
測定器７に伝達される速度が異なるため差圧測定器７の
出方信号は変動する。Of these, FIG. 3 is a graph showing changes in the output signal of the differential pressure measuring device 70. When a pressure fluctuation occurs in the steam dome 2 in the reactor pressure valley device 1, as mentioned above, the upper and lower pressures change. Since the speed of transmission to the differential pressure measuring device 7 differs depending on the length of the detection tubes 5 and 6 and the piping configuration, the output signal of the differential pressure measuring device 7 varies.
また、第４図は中性子束測定器１３の出方信号の変化を
示すグラフであり、この出方信号の変動は原子炉圧力容
器１内の蒸気ドーム２の圧力変動により燃料集合体１１
の出力が変動するためである。Further, FIG. 4 is a graph showing changes in the output signal of the neutron flux measuring device 13, and the fluctuations in the output signal are caused by pressure fluctuations in the steam dome 2 in the reactor pressure vessel 1.
This is because the output of
なお、原子炉圧力容器１内の定常的な圧力変動に対し、
差圧＋ｌＩ定器７および中性子束測定器１３の出力信号
は同一周期をもって震動することが多い。In addition, for steady pressure fluctuations in the reactor pressure vessel 1,
The output signals of the differential pressure +lI constant device 7 and the neutron flux measuring device 13 often oscillate with the same period.
前記差圧測定器７および中性子束＋＋ｉｌｌ定器［３の
出力信号は水位補正演算装置［０に入力され、この水位
補正演算装置ＩＯ内において差圧測定器７の出力信号は
中性子束測定器１３の出力信号により補正、演算される
。しかるに、再出力信号の周期は同一なので、圧力変動
の影鰺は見かけ上無視でき、第５図に示す水位補正演算
装置１０の出力１５号は安定した水位信号となって圧力
容器水位指示器８および圧力容器水位設定器９に入力さ
れる。したがって、安定した水位監視を行なうことがで
きる。The output signals of the differential pressure measuring device 7 and the neutron flux ++ill constant device [3 are input to the water level correction calculation device [0], and in this water level correction calculation device IO, the output signals of the differential pressure measuring device 7 are input to the neutron flux measuring device 13. Corrected and calculated based on the output signal of However, since the period of the re-output signal is the same, the effect of pressure fluctuation can be ignored in appearance, and the output No. 15 of the water level correction calculation device 10 shown in FIG. and is input to the pressure vessel water level setting device 9. Therefore, stable water level monitoring can be performed.
以上説明したように、本発明に係る沸騰水型原子炉の原
子炉圧力容器内の水位ａ［測装置は、原子炉の出力を測
定する中性子束測定器と、差圧測定器および中性子束測
定器の出力信号が入力されこの中性子束測定器の出力信
号によシ差圧測定器の出力信号を補正、演算する水位補
正演算装置とを有するので、正確でかつ安定した原子炉
圧力容器内の水位を計測することができる。As explained above, the water level a [measuring device] in the reactor pressure vessel of the boiling water reactor according to the present invention includes a neutron flux measuring device that measures the output of the reactor, a differential pressure measuring device, and a neutron flux measuring device. The output signal of the neutron flux measuring device is input to the water level correction calculation device which corrects and calculates the output signal of the differential pressure measuring device based on the output signal of the neutron flux measuring device. Water level can be measured.
第１図は従来の水位計測装置の説明図、第２図は本発明
に係る沸騰水型原子炉の原子炉圧力容器内の水位計測装
置の実施例を示す説明図、第３図。
第４図および第５図はそれぞれ差圧測定器、中性子束測
定器および水位補正演算装置の出力信号の変化を示すグ
ラフである。
１・・・原子炉圧力容器、２・・・蒸気ドーム、４・・
・蒸気凝縮槽、５，６・・・圧力検出管、７・・・差圧
測定器、ｌＯ・・・水位補正演算装置、１３・・・中性
子束測定器。
出願人代理人 波 多 野 久FIG. 1 is an explanatory diagram of a conventional water level measuring device, FIG. 2 is an explanatory diagram showing an embodiment of the water level measuring device in a reactor pressure vessel of a boiling water reactor according to the present invention, and FIG. FIGS. 4 and 5 are graphs showing changes in the output signals of the differential pressure measuring device, the neutron flux measuring device, and the water level correction calculation device, respectively. 1...Reactor pressure vessel, 2...Steam dome, 4...
- Steam condensing tank, 5, 6... Pressure detection tube, 7... Differential pressure measuring device, lO... Water level correction calculation device, 13... Neutron flux measuring device. Applicant's agent Hisashi Hatano
Claims (1)
蒸気凝縮伯と差圧測定器とを上部圧力検出管により接続
するとともに、前記原子炉圧力容器の上下方向中間位置
と前記差圧測定器とを下部圧力検出’ｔｌよシ接続し、
上部および下部圧力検出管の水柱差によシ原子炉圧力容
器内の水位を計測する水位計測装置において、原子炉の
出力を測定する中性子束測定器と、前記差圧測定２＆お
よび中性子束測定器の出力信号が人力され、この中性子
束測定器の出力信号により差圧測定器の出力信号を補正
、演算する水位補正演算装。 置とを有することを特徴とする沸騰水型原子炉の原子炉
圧力容器内の水位計測装置。 ２）前記中性子束測定器は、炉心部に設けられた中性子
束検出器の出力信号を人力される時６ｈ育求の範囲第１
項８Ｃ載の沸騰水型原子炉の原子炉圧力容器内の水位計
測装ＶＪ１゜[Claims] 1) A steam dome connected to the steam dome at the upper part of the reactor pressure vessel and a differential pressure measuring device are connected by an upper pressure detection tube, and at an intermediate position in the vertical direction of the reactor pressure vessel. and the differential pressure measuring device are connected to the lower pressure detection 'tl,
A water level measuring device that measures the water level in a reactor pressure vessel based on a water column difference between upper and lower pressure detection tubes, comprising: a neutron flux measuring device that measures the output of a nuclear reactor; and the differential pressure measuring device 2 and the neutron flux measuring device. The output signal of the neutron flux measuring device is input manually, and the output signal of the differential pressure measuring device is corrected and calculated using the output signal of the neutron flux measuring device. 1. A water level measuring device in a reactor pressure vessel of a boiling water reactor, characterized in that it has: 2) The neutron flux measuring device detects the output signal of the neutron flux detector installed in the reactor core within the first range of 6 hours of human input.
Water level measurement device VJ1゜ in the reactor pressure vessel of a boiling water reactor listed in Item 8C
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57213383A JPS59104593A (en) | 1982-12-07 | 1982-12-07 | Water level measuring device in pressure vessel of bwr type reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57213383A JPS59104593A (en) | 1982-12-07 | 1982-12-07 | Water level measuring device in pressure vessel of bwr type reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS59104593A true JPS59104593A (en) | 1984-06-16 |
Family
ID=16638286
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP57213383A Pending JPS59104593A (en) | 1982-12-07 | 1982-12-07 | Water level measuring device in pressure vessel of bwr type reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS59104593A (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4765945A (en) * | 1985-11-25 | 1988-08-23 | Kraftwerk Union Aktiengesellschaft | Method and apparatus for measuring the filling level in a reactor pressure vessel of a boiling-water reactor |
| JPH04196395A (en) * | 1990-11-28 | 1992-07-16 | Hitachi Ltd | Electronic computer and cooling device thereof |
| WO1996036970A1 (en) * | 1995-05-02 | 1996-11-21 | General Physics Corporation | Nuclear reactor coolant level monitoring system |
| CN1046286C (en) * | 1993-09-16 | 1999-11-10 | 明治制果株式会社 | Novel cephem derivative |
-
1982
- 1982-12-07 JP JP57213383A patent/JPS59104593A/en active Pending
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4765945A (en) * | 1985-11-25 | 1988-08-23 | Kraftwerk Union Aktiengesellschaft | Method and apparatus for measuring the filling level in a reactor pressure vessel of a boiling-water reactor |
| JPH04196395A (en) * | 1990-11-28 | 1992-07-16 | Hitachi Ltd | Electronic computer and cooling device thereof |
| CN1046286C (en) * | 1993-09-16 | 1999-11-10 | 明治制果株式会社 | Novel cephem derivative |
| WO1996036970A1 (en) * | 1995-05-02 | 1996-11-21 | General Physics Corporation | Nuclear reactor coolant level monitoring system |
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