JP2008116296A - Method and device for determining cut-off and damage of jet pump flow-rate measurement piping - Google Patents
Method and device for determining cut-off and damage of jet pump flow-rate measurement piping Download PDFInfo
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- JP2008116296A JP2008116296A JP2006299077A JP2006299077A JP2008116296A JP 2008116296 A JP2008116296 A JP 2008116296A JP 2006299077 A JP2006299077 A JP 2006299077A JP 2006299077 A JP2006299077 A JP 2006299077A JP 2008116296 A JP2008116296 A JP 2008116296A
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- 238000005259 measurement Methods 0.000 title claims abstract description 35
- 238000000034 method Methods 0.000 title claims description 19
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 33
- 238000009835 boiling Methods 0.000 claims abstract description 10
- 239000000498 cooling water Substances 0.000 claims description 11
- 238000011156 evaluation Methods 0.000 claims description 3
- 238000000691 measurement method Methods 0.000 claims 1
- 230000008439 repair process Effects 0.000 abstract description 4
- 238000002360 preparation method Methods 0.000 abstract description 2
- 238000007405 data analysis Methods 0.000 description 5
- 230000001052 transient effect Effects 0.000 description 4
- 230000000875 corresponding effect Effects 0.000 description 3
- 230000003595 spectral effect Effects 0.000 description 3
- 230000002596 correlated effect Effects 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 238000007664 blowing Methods 0.000 description 1
- 239000000284 extract Substances 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
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- 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
Abstract
Description
この発明は、沸騰水型原子炉の圧力容器内のアニュラス部からダウンカマ部へ冷却水を送るジェットポンプの流量計測用に、そのジェットポンプのディフーザ内とダウンカマ部との差圧を計測するための配管のうち、ディフーザからアニュラス部内に配設された配管の切損を判定する方法および、その方法に用いられるジェットポンプ流量計測配管切損判定装置に関するものである。 This invention is for measuring the differential pressure between the diffuser of a jet pump and the downcomer part for measuring the flow rate of the jet pump that sends cooling water from the annulus part to the downcomer part in the pressure vessel of the boiling water reactor. The present invention relates to a method for determining a breakage of a pipe disposed in an annulus portion from a diffuser, and a jet pump flow measurement pipe breakage determination apparatus used in the method.
沸騰水型原子炉（ＢＷＲ）においては、図４に示すように、圧力容器１内に、炉心２と、その炉心２を下方から支持する支持板３と、炉心２を側方から囲むシュラウド４と、シュラウド４の周囲のアニュラス部１ａにシュラウド４を囲むように配置されてそのアニュラス部１ａ内の冷却水を支持板３の下方のダウンカマ部１ｂへ送る多数の大型のジェットポンプ５とが設けられており、それらのジェットポンプ５は、それらのうちの２台について図５に詳細に示すように、冷却水を吸入する上向きに開いた吸入口５ａと、外部のポンプから圧力容器１内に送られた加圧水をその吸入口５ａ内に下向きに吹き込んでアニュラス部１ａ内の冷却水を吸入口５ａ内に引き込むノズル５ｂと、吸入口５ａ内に吸入された冷却水をダウンカマ部１ｂへ送る裁頭円錐状のディフーザ５ｃとを有している。 In a boiling water reactor (BWR), as shown in FIG. 4, in a pressure vessel 1, a core 2, a support plate 3 that supports the core 2 from below, and a shroud 4 that surrounds the core 2 from the side. And a large number of large jet pumps 5 disposed around the shroud 4 so as to surround the shroud 4 and sending the cooling water in the annulus portion 1a to the downcomer portion 1b below the support plate 3. These jet pumps 5 are, as shown in detail in FIG. 5 for two of them, an upwardly opened suction port 5a for sucking cooling water, and an external pump into the pressure vessel 1 The supplied pressurized water is blown downward into the suction port 5a and the cooling water in the annulus portion 1a is drawn into the suction port 5a, and the cooling water sucked into the suction port 5a is sent to the downcomer portion 1b. Court head and a cone-shaped diffuser 5c.
沸騰水型原子炉（ＢＷＲ）においてはまた、図４および図５に示すように、各ジェットポンプ５が送る水の流量を計測するために、各ジェットポンプ５のディフーザ５ｃ内の水圧を取り出す小口径配管６および、ダウンカマ部１ｂ内の水圧を取り出す小口径配管７と、それらの小口径配管６，７で取り出した水圧の差圧を計測する、各ジェットポンプ５に対応するジェットポンプ差圧計８とが設けられ、さらに圧力容器１内の各部の差圧を検出するために、シュラウド４内の炉心２の下方の位置１ｃの水圧を取り出す小口径配管９と、小口径配管７，９で取り出した水圧の差圧を計測する支持板差圧計１０と、シュラウド４内の炉心２の上方の位置１ｄの水圧を取り出す小口径配管１１と、小口径配管９，１１で取り出した水圧の差圧を計測する炉心差圧計１２とが設けられている。 In the boiling water reactor (BWR), as shown in FIGS. 4 and 5, in order to measure the flow rate of water sent by each jet pump 5, a small water pressure is taken out from the diffuser 5 c of each jet pump 5. A jet pump differential pressure gauge 8 corresponding to each jet pump 5 that measures the differential pressure between the bore pipe 6 and the small bore pipe 7 for taking out the water pressure in the downcomer portion 1b and the water pressure taken out through the small bore pipes 6 and 7. And a small-diameter pipe 9 for extracting water pressure at a position 1c below the core 2 in the shroud 4 and small-diameter pipes 7 and 9 for detecting the differential pressure of each part in the pressure vessel 1 The differential pressure of the water pressure extracted by the support plate differential pressure gauge 10 that measures the differential pressure of the water pressure, the small-diameter pipe 11 that extracts the water pressure at the position 1d above the core 2 in the shroud 4, and the small-diameter pipes 9 and 11 measurement And the core differential pressure gauge 12 is provided that.
ところで近年、ジェットポンプ５のディフーザ５ｃ内の水圧を取り出す上記小口径配管６の何れかが、ディフーザ５ｃからアニュラス部１ａ内に配設された例えば図中符号ＢＫで示す如き部分で、原子炉の運転中の振動の影響等を受けて切損する事象が散見されている。当該事象が原子炉の運転中に発生した場合、先ず、信号レベルの変化として発見できる場合もあるが、その場合でも、他の原因との区別は必ずしも明確にできない。このため原因が当該小口径配管６の切損であることの確認については、原子炉を停止させて圧力容器１の蓋を開放した後、水中テレビカメラを圧力容器１内に入れて行う必要がある。 Incidentally, in recent years, any of the small-diameter pipes 6 for taking out the water pressure in the diffuser 5c of the jet pump 5 is disposed in the annulus portion 1a from the diffuser 5c, for example, at a portion indicated by symbol BK in the figure. There are some events that are broken due to the influence of vibration during operation. If this event occurs during the operation of the reactor, it may be first detected as a change in signal level, but even in that case, it is not always clear from other causes. For this reason, it is necessary to confirm that the cause is the cut of the small-diameter pipe 6 by placing the underwater television camera in the pressure vessel 1 after stopping the reactor and opening the lid of the pressure vessel 1. is there.
すなわち従来、ジェットポンプ５のディフーザ５ｃ内の水圧を取り出す小口径配管６が切損する事象が原子炉の運転中に発生し、ジェットポンプ差圧計８の信号レベルに変化が現れても、それだけでは原因が当該小口径配管６の切損であるのか、あるいはそれ以外の要因（例えば当該小口径配管６への異物詰まり等）なのかは判別できず、対策を講じるにしても切損以外の要因の場合も考慮して準備しなければならなかったため、必ずしも効率の良い点検・補修作業の準備ができなかった。 That is, conventionally, an event that the small-diameter pipe 6 for taking out the water pressure in the diffuser 5c of the jet pump 5 is broken during the operation of the nuclear reactor, and even if the signal level of the jet pump differential pressure gauge 8 changes, that alone is the cause. Is a failure of the small-diameter pipe 6 or other factors (for example, clogging of foreign matter into the small-diameter pipe 6). Because we had to prepare in consideration of the case, we could not always prepare for efficient inspection and repair work.
従って、ジェットポンプ５の流量レベルに有意な変化が現れた際に、その原因がディフーザ５ｃ内の水圧を取り出す小口径配管６の切損であるか否かを明確に判定できること、また原子炉の運転中に定期的に繰り返して当該切損事象が発生していないことの確認ができることは、原子力プラントの効率的な運用・保守に繋がる課題であった。 Therefore, when a significant change appears in the flow rate level of the jet pump 5, it can be clearly determined whether or not the cause is a breakage in the small-diameter pipe 6 that takes out the water pressure in the diffuser 5c. Being able to confirm that the cutting event has not occurred repeatedly during operation was an issue that led to efficient operation and maintenance of the nuclear power plant.
この発明は、上記課題を有利に解決することを目的とするものであり、この発明のジェットポンプ流量計測配管切損判定方法は、沸騰水型原子炉内の炉心を囲むシュラウドの周囲のアニュラス部に設けられて、そのアニュラス部から、前記炉心を下方から支持する支持板の下のダウンカマ部へ冷却水を送るジェットポンプの流量計測用に、そのジェットポンプのディフーザ内と前記ダウンカマ部との差圧を計測するための配管のうち、前記ディフーザから前記アニュラス部内に配設された配管の切損を判定するに際し、前記ディフーザ内と前記ダウンカマ部との差圧である第１の差圧と、前記シュラウド内の前記炉心の下方の部位と前記ダウンカマ部との差圧または前記シュラウド内の前記炉心の上方の部位と前記炉心の下方の部位との差圧である第２の差圧とをそれぞれ計測し、それら計測した第１の差圧と第２の差圧との間の相関を評価して、相関が見られる場合に、前記ディフーザから前記アニュラス部内に配設された配管の切損が有ると判定することを特徴とするものである。 SUMMARY OF THE INVENTION An object of the present invention is to advantageously solve the above-described problem, and a jet pump flow measurement pipe breakage determination method according to the present invention includes an annulus portion around a shroud surrounding a core in a boiling water reactor. For measuring the flow rate of a jet pump that sends cooling water from its annulus to the downcomer below the support plate that supports the core from below, the difference between the inside of the diffuser of the jet pump and the downcomer Among the pipes for measuring the pressure, when determining the breakage of the pipe disposed in the annulus portion from the diffuser, a first differential pressure which is a differential pressure between the diffuser and the downcomer portion, Differential pressure between the lower part of the core in the shroud and the downcomer or the differential pressure between the upper part of the core and the lower part of the core in the shroud Each second differential pressure is measured, the correlation between the measured first differential pressure and the second differential pressure is evaluated, and when a correlation is found, the diffuser enters the annulus portion. It is determined that there is a breakage in the disposed piping.
そして上記方法に用いられるこの発明のジェットポンプ流量計測配管切損判定装置は、前記ディフーザ内と前記ダウンカマ部との差圧である第１の差圧を計測する第１の差圧計と、前記シュラウド内の前記炉心の下方の部位と前記ダウンカマ部との差圧または前記シュラウド内の前記炉心の上方の部位と前記炉心の下方の部位との差圧である第２の差圧を計測する第２の差圧計と、それら第１の差圧計が計測した第１の差圧と第２の差圧計が計測した第２の差圧との間の相関を評価して、相関が見られる場合に、前記ディフーザから前記アニュラス部内に配設された配管の切損が有ると判定する切損判定手段と、を具えることを特徴とするものである。 The jet pump flow measurement pipe breakage determination device of the present invention used in the above method includes a first differential pressure gauge that measures a first differential pressure that is a differential pressure between the diffuser and the downcomer portion, and the shroud. A second differential pressure is measured which is a second differential pressure which is a differential pressure between a portion below the core in the core and the downcomer portion or a pressure difference between the portion above the core in the shroud and the portion below the core. When the correlation between the first differential pressure gauge measured by the first differential pressure gauge and the second differential pressure measured by the second differential pressure gauge is evaluated and a correlation is found, And a breakage determining means for determining that there is a breakage in the pipe disposed in the annulus portion from the diffuser.
ジェットポンプの流量は、ジェットポンプのディフーザ内とダウンカマ部との差圧である第１の差圧から換算して計測しているので、そのディフーザ内とダウンカマ部との差圧を計測するための配管のうち、ディフーザからアニュラス部内に配設された配管に切損が起こった場合、切損部分でその配管がアニュラス部内に開放されて、本来はディフーザ内とダウンカマ部との差圧であるはずの第１の差圧を示す第１の差圧計の出力信号が、実質的にはアニュラス部とダウンカマ部との差圧を示していることになる。この場合、アニュラス部とシュラウドの内側の炉心の上下方の位置とはシュラウドの上方を経由して連通していることから、その第１の差圧（第１の差圧計の出力信号）は、それまで特に相関の見られなかった、シュラウド内の前記炉心の下方の部位と前記ダウンカマ部との差圧または前記シュラウド内の前記炉心の上方の部位と前記炉心の下方の部位との差圧である第２の差圧（第２の差圧計の出力信号）との間に有意な相関を示現するようになる。 Since the flow rate of the jet pump is converted from the first differential pressure, which is the differential pressure between the diffuser and the downcomer of the jet pump, it is used to measure the differential pressure between the diffuser and the downcomer. If a pipe breaks in the annulus part from the diffuser, the pipe is opened to the annulus part at the broken part, which should be the pressure difference between the diffuser and the downcomer part. The output signal of the first differential pressure gauge indicating the first differential pressure substantially indicates the differential pressure between the annulus portion and the downcomer portion. In this case, since the annulus portion and the position above and below the core inside the shroud communicate with each other via the top of the shroud, the first differential pressure (the output signal of the first differential pressure gauge) is The differential pressure between the lower part of the core in the shroud and the downcomer or the differential pressure between the upper part of the core in the shroud and the lower part of the core, which had not been particularly correlated until then. A significant correlation is exhibited with a certain second differential pressure (output signal of the second differential pressure gauge).
しかしてこの発明のジェットポンプ流量計測配管切損判定方法によれば、それら第１の差圧計が計測した第１の差圧と第２の差圧計が計測した第２の差圧との間の相関を評価して、相関が見られる場合に、ディフーザからアニュラス部内に配設された配管の切損が有ると判定するので、その配管が切損している状態にあるか否かを明確に判定することができる。 Therefore, according to the jet pump flow measurement pipe breakage determination method of the present invention, the difference between the first differential pressure measured by the first differential pressure gauge and the second differential pressure measured by the second differential pressure gauge. When the correlation is evaluated and the correlation is found, it is determined that the pipe disposed in the annulus from the diffuser is broken, so it is clearly determined whether or not the pipe is broken. can do.
またこの発明のジェットポンプ流量計測配管切損判定装置によれば、切損判定手段が、それら第１の差圧計が計測した第１の差圧と第２の差圧計が計測した第２の差圧との間の相関を評価して、相関が見られる場合に、ディフーザからアニュラス部内に配設された配管の切損が有ると判定するので、その配管が切損している状態にあるか否かを自動的に明確に判定することができる。 Further, according to the jet pump flow measurement pipe breakage judging device of the present invention, the breakage judging means has the first differential pressure measured by the first differential pressure gauge and the second difference measured by the second differential pressure gauge. When the correlation between the pressure and the pressure is evaluated and a correlation is seen, it is determined that the pipe disposed in the annulus portion is broken from the diffuser, so whether or not the pipe is broken. Can be automatically and clearly determined.
なお、この発明においては、前記相関の評価に、コヒーレンス値を指標として用いても良い。 In the present invention, a coherence value may be used as an index for the correlation evaluation.
また。この発明においては、前記第２の差圧は、前記シュラウド内の前記炉心の下方の部位と前記ダウンカマ部との差圧としても良い。 Also. In the present invention, the second differential pressure may be a differential pressure between a portion of the shroud below the core and the downcomer portion.
以下、本発明の実施の形態を実施例によって、図面に基づき詳細に説明する。ここに、図１は、この発明のジェットポンプ流量計測配管切損判定方法の一実施例およびそこに用いられるこの発明のジェットポンプ流量計測配管切損判定装置の構成を示す構成図、図２は、その実施例のジェットポンプ流量計測配管切損判定装置が上記実施例の方法に基づき切損を判定する場合のコヒーレンス値の求め方を示すフローチャート、図３は、上記実施例のジェットポンプ流量計測配管切損判定装置が上記実施例の方法に基づき切損有りと判定する場合のコヒーレンス値の変化状態を例示するグラフを示すカラー写真である。 Hereinafter, embodiments of the present invention will be described in detail with reference to the drawings. FIG. 1 is a block diagram showing the configuration of an embodiment of the jet pump flow measurement pipe breakage determination method of the present invention and the configuration of the jet pump flow measurement pipe breakage determination apparatus of the present invention used therein, and FIG. FIG. 3 is a flowchart showing how to obtain a coherence value when the jet pump flow measurement pipe breakage determination apparatus of the embodiment determines a breakage based on the method of the embodiment, and FIG. 3 shows the jet pump flow measurement of the embodiment. It is a color photograph which shows the graph which illustrates the change state of a coherence value in case a pipe breakage determination apparatus determines with a cut based on the method of the said Example.
この実施例のジェットポンプ流量計測配管切損判定装置は、図４および図５に示す従来のものと同様の原子炉に設けられているものであり、図１中、図４および図５におけると同様の部分は、それと同一の符号にて示す。 The jet pump flow measurement pipe breakage judgment device of this embodiment is provided in the same nuclear reactor as the conventional one shown in FIGS. 4 and 5, and in FIG. 1 and FIG. Similar parts are denoted by the same reference numerals.
すなわち、この実施例のジェットポンプ流量計測配管切損判定装置が設けられた沸騰水型原子炉（ＢＷＲ）も、図４および図５に示すように、圧力容器１内に、炉心２と、図１では図示しないが、その炉心２を下方から支持する支持板３と、炉心２を側方から囲むシュラウド４と、シュラウド４の周囲のアニュラス部１ａにシュラウド４を囲むように配置されてそのアニュラス部１ａ内の冷却水を支持板３の下方のダウンカマ部１ｂへ送る多数の大型のジェットポンプ５とが設けられており、それらのジェットポンプ５は、冷却水を吸入する上向きに開いた吸入口５ａと、外部のポンプから圧力容器１内に送られた加圧水をその吸入口５ａ内に下向きに吹き込んでアニュラス部１ａ内の冷却水を吸入口５ａ内に引き込むノズル５ｂと、吸入口５ａ内に吸入された冷却水をダウンカマ部１ｂへ送る裁頭円錐状のディフーザ５ｃとを有している。 That is, the boiling water reactor (BWR) provided with the jet pump flow measurement pipe breakage determination device of this embodiment is also provided in the pressure vessel 1 with the core 2 and the figure as shown in FIGS. Although not shown in FIG. 1, a support plate 3 that supports the core 2 from below, a shroud 4 that surrounds the core 2 from the side, and an annulus that surrounds the shroud 4 in an annulus portion 1 a around the shroud 4. There are provided a large number of large jet pumps 5 for sending the cooling water in the portion 1a to the downcomer portion 1b below the support plate 3, and these jet pumps 5 are suction ports opened upward for sucking the cooling water. 5a, a nozzle 5b for blowing the pressurized water sent from the external pump into the pressure vessel 1 downward into the suction port 5a and drawing the cooling water in the annulus portion 1a into the suction port 5a, and the suction port The cooling water sucked into a and a diffuser 5c frusto conical sent to the downcomer portion 1b.
この沸騰水型原子炉においてはまた、各ジェットポンプ５が送る水の流量を計測するために、各ジェットポンプ５のディフーザ５ｃ内の水圧を取り出す小口径配管６および、ダウンカマ部１ｂ内の水圧を取り出す小口径配管７と、第１の差圧としての、それらの小口径配管６，７で取り出した水圧の差圧を計測する、第１の差圧計としての、各ジェットポンプ５に対応するジェットポンプ差圧計８とが設けられ、さらに圧力容器１内の各部の差圧を検出するために、シュラウド４内の炉心２の下方の位置１ｃの水圧を取り出す小口径配管９と、この実施例では第２の差圧としての、小口径配管７，９で取り出した水圧の差圧を計測する、第２の差圧計としての支持板差圧計１０と、シュラウド４内の炉心２の上方の位置１ｄの水圧を取り出す小口径配管１１と、小口径配管９，１１で取り出した水圧の差圧を計測する炉心差圧計１２とが設けられており、それらジェットポンプ差圧計８と支持板差圧計１０と炉心差圧計１２とは計測系１３を構成している。 In this boiling water reactor, in order to measure the flow rate of water sent by each jet pump 5, the small-diameter pipe 6 for taking out the water pressure in the diffuser 5c of each jet pump 5 and the water pressure in the downcomer portion 1b are used. A jet corresponding to each jet pump 5 as a first differential pressure gauge that measures the differential pressure between the small-diameter pipe 7 to be taken out and the water pressure taken out by the small-diameter pipes 6 and 7 as the first differential pressure. A pump differential pressure gauge 8 is provided, and a small-diameter pipe 9 for taking out water pressure at a position 1c below the core 2 in the shroud 4 in order to detect the differential pressure of each part in the pressure vessel 1, and in this embodiment A support plate differential pressure gauge 10 as a second differential pressure gauge for measuring the differential pressure of the water pressure taken out by the small-diameter pipes 7 and 9 as the second differential pressure, and a position 1d above the core 2 in the shroud 4 Take out the water pressure of There are provided a core pipe 11 and a core differential pressure gauge 12 for measuring the differential pressure of the water pressure taken out by the small diameter pipes 9, 11. These jet pump differential pressure gauge 8, support plate differential pressure gauge 10, and core differential pressure gauge 12 Constitutes the measurement system 13.
この沸騰水型原子炉においてはさらに、計測系１３のジェットポンプ差圧計８と支持板差圧計１０と炉心差圧計１２とがそれぞれ計測したアナログの差圧信号を高頻度でデジタル信号に変換して実質上連続的に記録するデータ記録処理装置としての、例えばハードディスクドライブ装置を有する過渡現象記録装置１４と、その過渡現象記録装置１４からこの実施例ではジェットポンプ差圧計８の差圧信号と支持板差圧計１０の差圧信号とをデジタルデータとして読み出して解析する、切損判定手段としての、通常のパーソナルコンピュータで構成されたデータ解析装置１５とが設けられている。従って、この実施例ではジェットポンプ差圧計８と支持板差圧計１０とデータ解析装置１５とが、ジェットポンプ流量計測配管切損判定装置を構成している。 In this boiling water reactor, the analog differential pressure signals respectively measured by the jet pump differential pressure gauge 8, the support plate differential pressure gauge 10, and the core differential pressure gauge 12 of the measurement system 13 are converted into digital signals at a high frequency. As a data recording processing device for recording substantially continuously, for example, a transient phenomenon recording device 14 having a hard disk drive device, and from the transient phenomenon recording device 14 in this embodiment, a differential pressure signal and a support plate of the jet pump differential pressure gauge 8 There is provided a data analysis device 15 constituted by a normal personal computer as a breakage determination means for reading and analyzing the differential pressure signal of the differential pressure gauge 10 as digital data. Therefore, in this embodiment, the jet pump differential pressure gauge 8, the support plate differential pressure gauge 10, and the data analysis device 15 constitute a jet pump flow measurement pipe breakage determination device.
この沸騰水型原子炉においては、各ジェットポンプ５の流量は、ジェットポンプ５のディフーザ５ｃ内とダウンカマ部１ｂとの差圧である第１の差圧から換算して計測しているので、そのディフーザ５ｃ内とダウンカマ部１ｂとの差圧を計測するための配管６，７のうち、ディフーザ５ｃ内の水圧を取り出す小口径配管６の、ディフーザ５ｃからアニュラス部１ａ内に配設された部分に切損が起こった場合、切損部分でその配管６がアニュラス部１ａ内に開放されて、本来はディフーザ５ｃ内とダウンカマ部１ｂとの差圧であるはずの第１の差圧を示すジェットポンプ差圧計８の出力信号が、実質的にはアニュラス部１ａとダウンカマ部１ｂとの差圧を示していることになる。 In this boiling water reactor, the flow rate of each jet pump 5 is measured in terms of the first differential pressure which is the differential pressure between the diffuser 5c of the jet pump 5 and the downcomer portion 1b. Of the pipes 6 and 7 for measuring the differential pressure between the diffuser 5c and the downcomer portion 1b, a portion of the small-diameter pipe 6 for taking out the water pressure in the diffuser 5c from the diffuser 5c into the annulus portion 1a. When a cut occurs, the pipe 6 is opened in the annulus portion 1a at the cut portion, and the jet pump showing the first differential pressure that should be the differential pressure between the diffuser 5c and the downcomer portion 1b. The output signal of the differential pressure gauge 8 substantially indicates the differential pressure between the annulus portion 1a and the downcomer portion 1b.
この場合、アニュラス部１ａとシュラウド４の内側の炉心２の上方および下方の位置とはシュラウド４の上方を経由して連通していることから、その第１の差圧（ジェットポンプ差圧計８の出力信号）は、それまで特に相関の見られなかった、シュラウド４内の炉心２の下方の部位とダウンカマ部１ｂとの差圧である第２の差圧（支持板差圧計１０の出力信号）との間に有意な相関を示現するようになる。 In this case, since the annulus portion 1a and the position above and below the core 2 inside the shroud 4 communicate with each other via the top of the shroud 4, the first differential pressure (jet pump differential pressure gauge 8 Output signal) is a second differential pressure (output signal of the support plate differential pressure gauge 10), which is the differential pressure between the portion below the core 2 in the shroud 4 and the downcomer portion 1b, which has not been particularly correlated until then. A significant correlation is exhibited.
しかしてこの実施例のジェットポンプ流量計測配管切損判定方法では、この実施例のジェットポンプ流量計測配管切損判定装置の一部をなすデータ解析装置１５が、あらかじめ与えられたプログラムに基づき、それらジェットポンプ差圧計８の出力信号である第１の差圧と支持板差圧計１０の出力信号である第２の差圧とを過渡現象記録装置１４から高頻度（例えば数十ミリ秒間隔）で読み出してそれら第１の差圧と第２の差圧との間の相関を評価して、所定レベル以上の相関が見られる場合に、ディフーザ５ｃからアニュラス部１ａ内に配設された小口径配管６の切損が有ると判定する。 However, in the jet pump flow measurement pipe breakage determination method of this embodiment, the data analysis device 15 that forms a part of the jet pump flow measurement pipe breakage determination apparatus of this embodiment is based on a program given in advance. The first differential pressure that is an output signal of the jet pump differential pressure gauge 8 and the second differential pressure that is an output signal of the support plate differential pressure gauge 10 are frequently transmitted from the transient recording device 14 (for example, at intervals of several tens of milliseconds). When the correlation between the first differential pressure and the second differential pressure is read out and a correlation of a predetermined level or more is found, the small-diameter pipe disposed in the annulus portion 1a from the diffuser 5c It is determined that there are 6 cuts.
ここで、第１の差圧と第２の差圧との間の相関の評価は、例えば図２に示す如き手順でコヒーレンス値を求め、それを用いることで行うことができる。先ず、例えば第１の差圧を表す時系列信号ｘ（ｔ）のノイズ成分を分析するために、その時系列信号を三角波の和として近似する（フーリエ変換を行う）。 Here, the evaluation of the correlation between the first differential pressure and the second differential pressure can be performed, for example, by obtaining a coherence value by a procedure as shown in FIG. 2 and using it. First, in order to analyze the noise component of the time series signal x (t) representing the first differential pressure, for example, the time series signal is approximated as a sum of triangular waves (Fourier transform is performed).
次いで、フーリエ成分Ｘ（ｆ）から、下式により時系列信号ｘ（ｔ）に対応するパワースペクトル密度分布Ｐｘ（ｆ）が定義される。 Next, a power spectral density distribution Px (f) corresponding to the time series signal x (t) is defined from the Fourier component X (f) by the following equation.
同様に、例えば第２の差圧を表す他の時系列信号ｙ（ｔ）に対してもフーリエ成分Ｙ（ｆ）からパワースペクトル密度分布Ｐｙ（ｆ）が定義でき、合わせてクロススペクトル密度分布Ｓ（ｆ）も定義できる。 Similarly, the power spectral density distribution Py (f) can be defined from the Fourier component Y (f) for other time series signals y (t) representing the second differential pressure, for example, and the cross spectral density distribution S is combined. (F) can also be defined.
上述した式を用いて次式でコヒーレンス値Ｃｏｈ（ｆ）を定義し、これを相関を示す指標として用いる。 The coherence value Coh (f) is defined by the following equation using the above-described equation, and this is used as an index indicating the correlation.
図３は、この実施例のジェットポンプ流量計測配管切損判定装置がこの実施例のジェットポンプ流量計測配管切損判定方法に基づき切損有りと判定する場合のコヒーレンス値の変化状態を例示しており、具体的にはＪＰ−０１〜２０の２０台のジェットポンプ５のうち、図中曲線Aで示すＪＰ−１６のコヒーレンス値が、周波数１Ｈｚ以下の領域で他のジェットポンプより極めて大きくなっている。この図からも明らかなように、データ解析装置１５は、例えば周波数１０−１Ｈｚあるいはそれ以下の領域において例えばコヒーレンス値０．５および０．８を閾値として、求めたコヒーレンス値が０．５以上で０．８未満の場合は切損の徴候有り、求めたコヒーレンス値が０．８以上の場合は切損有り、求めたコヒーレンス値が０．５未満の場合は切損なしと判定することにより、ＪＰ−０１〜２０の２０台のジェットポンプ５の小口径配管６が各々切損している状態にあるか否かを、切損の徴候を含めて自動的に明確に判定することができる。 FIG. 3 exemplifies the change state of the coherence value when the jet pump flow measurement pipe breakage determination device of this embodiment determines that there is breakage based on the jet pump flow measurement pipe breakage determination method of this embodiment. Specifically, among the 20 jet pumps 5 of JP-01 to JP-01, the coherence value of JP-16 indicated by the curve A in the figure is much larger than that of other jet pumps in the frequency region of 1 Hz or less. Yes. As is apparent from this figure, the data analysis device 15 has a coherence value of 0.5 or more, for example, in the region of the frequency 10 −1 Hz or lower with the coherence values 0.5 and 0.8 as threshold values, for example. If it is less than 0.8, there is a sign of cutting, and if the calculated coherence value is 0.8 or more, there is cutting, and if the calculated coherence value is less than 0.5, it is determined that there is no cutting. It can be automatically and clearly determined whether or not the small-diameter pipes 6 of the 20 jet pumps 5 of JP-01 to 20 are broken, including signs of breakage.
以上、図示例に基づき説明したが、この発明は上述の例に限定されるものでなく、例えば、切損判定手段は、コヒーレンス値を用いる代わりに相関係数を用いて所定以上の相関があるか否かを評価しても良い。また第２の差圧は、小口径配管９，１１で取り出した水圧の差圧とし、第２の差圧計はそれを計測する炉心差圧計１２としても良い。 Although the present invention has been described based on the illustrated example, the present invention is not limited to the above-described example. For example, the cut determination unit has a correlation greater than a predetermined value using a correlation coefficient instead of using a coherence value It may be evaluated whether or not. Further, the second differential pressure may be the differential pressure of the water pressure taken out by the small-diameter pipes 9 and 11, and the second differential pressure gauge may be the core differential pressure gauge 12 for measuring it.
かくしてこの発明のジェットポンプ流量計測配管切損判定方法およびそこに用いられる装置によれば、原子炉の運転中においても、ジェットポンプ流量計測配管が切損状態にあるか否かを明確に判定することができ、これにより、原子炉停止中の水中テレビカメラによる撮影を待たなくても修理・補修の準備を開始することができる。 Thus, according to the jet pump flow measurement pipe breakage determination method and the apparatus used therefor according to the present invention, it is clearly determined whether or not the jet pump flow measurement pipe is broken even during the operation of the nuclear reactor. This makes it possible to start preparations for repairs and repairs without having to wait for underwater television camera shooting while the reactor is stopped.
また、ジェットポンプ流量計測配管が切損していないことを、原子炉の運転中に定期的に繰り返して確認することができる。 In addition, it can be confirmed periodically during operation of the reactor that the jet pump flow rate measurement piping is not broken.
１ 圧力容器
１ａ アニュラス部
１ｂ ダウンカマ部
１ｃ 炉心の下方の位置
１ｄ 炉心の上方の位置
２ 炉心
３ 支持板
４ シュラウド
５ ジェットポンプ
５ａ 吸入口
５ｂ ノズル
５ｃ ディフーザ
６，７，９，１１ 小口径配管
８ ジェットポンプ差圧計
１０ 支持板差圧計
１２ 炉心差圧計
１３ 計測系
１４ 過渡現象記録装置
１５ データ解析装置
DESCRIPTION OF SYMBOLS 1 Pressure vessel 1a Annulus part 1b Downcomer part 1c Position below the core 1d Position above the core 2 Core 3 Support plate 4 Shroud 5 Jet pump 5a Inlet 5b Nozzle 5c Diffuser 6, 7, 9, 11 Small diameter piping 8 Jet Pump differential pressure gauge 10 Support plate differential pressure gauge 12 Core differential pressure gauge 13 Measurement system 14 Transient phenomenon recording device 15 Data analysis device
Claims (4)
前記ディフーザ内と前記ダウンカマ部との差圧である第１の差圧と、前記シュラウド内の前記炉心の下方の部位と前記ダウンカマ部との差圧または前記シュラウド内の前記炉心の上方の部位と前記炉心の下方の部位との差圧である第２の差圧とをそれぞれ計測し、
それら計測した第１の差圧と第２の差圧との間の相関を評価して、相関が見られる場合に、前記ディフーザから前記アニュラス部内に配設された配管の切損が有ると判定することを特徴とする、ジェットポンプ流量計測配管切損判定方法。 A jet pump that is provided in an annulus around a shroud surrounding a core in a pressure vessel of a boiling water reactor and sends cooling water from the annulus to a downcomer below a support plate that supports the core from below Among the pipes for measuring the differential pressure between the diffuser of the jet pump and the downcomer part for measuring the flow rate of the pipe, when determining the breakage of the pipe disposed in the annulus part from the diffuser,
A first differential pressure which is a differential pressure between the diffuser and the downcomer portion; a differential pressure between a portion below the core in the shroud and the downcomer portion; or a portion above the core in the shroud. Measure the second differential pressure, which is the differential pressure with the lower part of the core,
The correlation between the measured first differential pressure and the second differential pressure is evaluated, and when the correlation is found, it is determined that there is a breakage in the pipe disposed in the annulus portion from the diffuser. A jet pump flow rate measurement method for determining pipe breakage.
前記シュラウド内の前記炉心の下方の部位と前記ダウンカマ部との差圧または前記シュラウド内の前記炉心の上方の部位と前記炉心の下方の部位との差圧である第２の差圧を計測する第２の差圧計と、
それら第１の差圧計が計測した第１の差圧と第２の差圧計が計測した第２の差圧との間の相関を評価して、相関が見られる場合に、前記ディフーザから前記アニュラス部内に配設された配管の切損が有ると判定する切損判定手段と、
を具えることを特徴とする、請求項１から３までの何れか記載のジェットポンプ流量計測配管切損判定方法に用いられるジェットポンプ流量計測配管切損判定装置。 A first differential pressure gauge that measures a first differential pressure that is a differential pressure between the diffuser and the downcomer portion;
A second differential pressure that is a differential pressure between a portion below the core in the shroud and the downcomer portion or a differential pressure between a portion above the core and a portion below the core in the shroud is measured. A second differential pressure gauge;
The correlation between the first differential pressure measured by the first differential pressure gauge and the second differential pressure measured by the second differential pressure gauge is evaluated, and when a correlation is found, the diffuser determines the annulus. A breakage judging means for judging that there is a breakage of the pipe disposed in the section;
A jet pump flow rate measurement pipe breakage judging device used in the jet pump flow rate measurement pipe breakage judgment method according to any one of claims 1 to 3.
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| GB2520432A (en) * | 2013-11-15 | 2015-05-20 | Caltec Ltd | A system for production boosting and measuring flow rate in a pipeline |
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| GB2520432A (en) * | 2013-11-15 | 2015-05-20 | Caltec Ltd | A system for production boosting and measuring flow rate in a pipeline |
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