JP2004020410A - Fuel supporting fixture filter inspection device and inspection method - Google Patents

Fuel supporting fixture filter inspection device and inspection method Download PDF

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JP2004020410A
JP2004020410A JP2002176610A JP2002176610A JP2004020410A JP 2004020410 A JP2004020410 A JP 2004020410A JP 2002176610 A JP2002176610 A JP 2002176610A JP 2002176610 A JP2002176610 A JP 2002176610A JP 2004020410 A JP2004020410 A JP 2004020410A
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filter
support fitting
fuel
fuel support
water
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JP3944004B2 (en
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Tatsuma Kato
加藤　竜馬
Hiroshi Komiya
小宮　浩
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Toshiba Corp
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Toshiba Corp
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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

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Abstract

<P>PROBLEM TO BE SOLVED: To inspect variation of pressure loss due to clad adhesion and the situation of choking due to debris in filters attached nearby core inlet of a reactor during the operation stop of reactor. <P>SOLUTION: A pressure loss inspection device 10 is attached underwater to a fuel supporting fixture after removing a fuel assembly from the fuel supporting fixture 40. It has a tube 11 connected to the fuel supporting fixture after removing the fuel assembly, a pump 13 driving water flow passing the filter and coming in the tube a flow meter (for example, venturi tube) 12 for measuring the flow in the tube and a pressure loss measuring means for measuring the pressure loss of the filter. In the other embodiment of the invention, a visual inspection system 20 of the filter has a camera 21 and an illumination device 22 capable of approaching a filter underwater from the inside and outside of the fuel supporting fixture. <P>COPYRIGHT: (C)2004,JPO

Description

【０００１】
【発明の属する技術分野】
本発明は、原子炉の炉心入口部付近に取り付けられたフィルタを、定期検査時などの原子炉停止時に検査するための検査装置および検査方法に関する。
【０００２】
【従来の技術】
一般に、原子炉内に設置された機器には、炉水に含まれるクラッドが表面に付着する可能性がある。クラッド付着状況を確認する方法として、通常は、原子炉が停止している定期検査中に、水中カメラを炉水中に入れ、該当する部位をカメラで見て確認する方法がとられている。
【０００３】
最近、冷却材中に含まれる固体の異物（デブリ）を炉心に入る前に捕捉するために、炉心入口部付近にデブリフィルタを取り付けることが検討されている（例えば、特開平７−２５３４９１号公報、特開平４−２３０８９２号公報参照）。しかし、実際の運転プラントへの適用実績がなく、経年によるクラッド付着の状況や、クラッド付着による影響を検査する方法はまだ確立されていない。
【０００４】
【発明が解決しようとする課題】
しかしながら、デブリフィルタの圧力損失（圧損）は炉心流量に大きな影響を与える重要な要因である。このため、クラッド付着による圧損の変化を定量的に計測する必要がある。また特に、デブリフィルタの穴が内部で曲がっている場合は、カメラで見ただけでは、表面のみ目視可能であるが、内部の状況は見えない。このため、捕捉したデブリによるデブリフィルタの目詰まり状況の確認ができない。
【０００５】
本発明はかかる従来の事情に対処してなされたものであり、運転プラントの炉心入口部付近に取り付けられたフィルタについて、プラントの運転停止中に、クラッド付着による圧損の変化やデブリなどによる目詰まり状況を検査できる装置および方法を提供することを目的とする。
【０００６】
【課題を解決するための手段】
本発明は上記目的の少なくとも一部を達成するものであって、請求項１に記載の発明は、原子炉内で燃料集合体を支持し、フィルタを通して前記燃料集合体に水を導入するための燃料支持金具から、前記原子炉の運転停止時に、前記燃料集合体を水中で外したあとにその燃料支持金具に水中で取り付けられて、前記フィルタの圧力損失を検査する燃料支持金具フィルタ検査装置において、前記燃料集合体を外したあとの前記燃料支持金具に接続される管と、前記フィルタを通って前記管に入る水の流れを駆動するポンプと、前記管内の流量を測定する流量計と、前記フィルタの圧力損失を測定する圧損測定手段と、を有することを特徴とする。
【０００７】
請求項１の発明によれば、原子炉の運転停止時に、燃料支持金具を炉内に設置した状態で、フィルタの圧損を定量的に計測でき、クラッド付着による圧損の経年変化を検査することができる。
【０００８】
また、請求項２に記載の発明は、請求項１に記載の燃料支持金具フィルタ検査装置において、前記流量計はベンチュリ管を用いるものであること、を特徴とする。請求項２の発明によれば、請求項１の発明による作用・効果が得られるほか、管内の流量を容易に測定することができる。
【０００９】
また、請求項３に記載の発明は、請求項１または２に記載の燃料支持金具フィルタ検査装置において、前記圧損測定手段は、前記管内の圧力を測定する手段を含むこと、を特徴とする。請求項３の発明によれば、請求項１または２の発明による作用・効果が得られるほか、フィルタの圧損測定を容易に行なうことができる。
【００１０】
また、請求項４に記載の発明は、原子炉内で燃料集合体を支持して前記燃料集合体に水を導入するための燃料支持金具に取り付けられたフィルタの圧力損失を検査する燃料支持金具フィルタ検査方法において、前記原子炉の運転停止時に、水中で前記燃料支持金具から前記燃料集合体を外す取り外し工程と、前記取り外し工程の後に前記燃料支持金具に水中で燃料支持金具フィルタ圧損検査装置を取り付ける取り付け工程と、前記取り付け工程の後に、前記燃料支持金具フィルタ圧損検査装置のポンプを駆動して前記フィルタを通る水の流れを作る流動工程と、前記流動工程における前記フィルタを通る水の流量および前記フィルタでの圧力損失を測定する測定工程と、を有することを特徴とする。
【００１１】
請求項４の発明によれば、原子炉の運転停止時に、燃料支持金具を炉内に設置した状態で、フィルタの圧損を定量的に計測でき、クラッドなどの付着による圧損の経年変化を検査することができる。
【００１２】
また、請求項５に記載の発明は、原子炉内で燃料集合体を支持し、フィルタを通して前記燃料集合体に水を導入するための燃料支持金具から、前記原子炉の運転停止時に、前記燃料集合体を外したあとにその燃料支持金具の内側および外側から前記フィルタを水中で目視観察するための燃料支持金具フィルタ検査装置であって、水中で、前記燃料支持金具の内側および外側から前記フィルタに近づけることのできるカメラおよび照明具を有すること、を特徴とする。
【００１３】
請求項５の発明によれば、原子炉の運転停止時に、燃料支持金具を炉内に設置した状態で、フィルタの流路穴の状況を明るく照らしながら目視観察することができる。
【００１４】
また、請求項６に記載の発明は、請求項５に記載の燃料支持金具フィルタ検査装置において、前記カメラと照明具が前記フィルタをはさんで向かい合って配置されるように構成されていること、を特徴とする。請求項６の発明によれば、請求項５の発明による作用・効果が得られるほか、背面からの光によってフィルタの流路穴の内部を鮮明に目視観察することができる。
【００１５】
また、請求項７に記載の発明は、原子炉内で燃料集合体を支持して前記燃料集合体に水を導入するための燃料支持金具に取り付けられたフィルタを検査する燃料支持金具フィルタ検査方法において、前記原子炉の運転停止時に、水中で前記燃料支持金具から前記燃料集合体を外す取り外し工程と、前記取り外し工程の後に、水中で、カメラおよび照明具を前記フィルタに近づけて当該フィルタを目視観測する観測工程と、を有することを特徴とする。
【００１６】
請求項７の発明によれば、原子炉の運転停止時に、燃料支持金具を炉内に設置した状態で、フィルタの流路穴の状況を明るく照らしながら目視観察することができる。
【００１７】
また、請求項８に記載の発明は、請求項７に記載の燃料支持金具フィルタ検査方法において、前記観測工程は、前記カメラと照明具が前記フィルタをはさんで向かい合って配置した状態で行なわれること、を特徴とする。請求項８の発明によれば、請求項７の発明による作用・効果が得られるほか、背面からの光によってフィルタの流路穴の内部を鮮明に目視観察することができる。
【００１８】
【発明の実施の形態】
以下に本発明に係る燃料支持金具フィルタ検査装置および検査方法の実施の形態を図面を参照して説明する。ここで、共通または類似の部分には共通の符号を付して、重複説明は適宜省略する。
【００１９】
まず、本発明に係る燃料支持金具フィルタ検査装置の第１の実施の形態を図１〜図３を参照して説明する。
図２は沸騰水型原子炉の燃料支持金具４０を示す。図示のように、上部に４個の開口６０があって、それぞれに燃料集合体（図示せず）が載置される。各開口６０に向かって燃料支持金具４０内に冷却材流路が形成されており、燃料支持金具４０の入口は水平方向外側を向いて開いていて、各入口にはデブリフィルタ３０が取り付けられている。燃料支持金具４０の中央には水平断面が十字形の制御棒（図示せず）が鉛直方向に貫通できるように水平断面が十字形の制御棒穴６１が形成されている。
【００２０】
この燃料支持金具４０は、図１に示すように、炉心支持板５０に設けられた穴に途中まで入って支持されている。さらに、燃料支持金具４０の真下に制御棒案内管５２が配置されている。なお、図１には燃料支持金具４０および制御棒案内管５２をそれぞれ１個だけ示されているが、これらは、それぞれ複数が水平方向に格子状に配列される。
【００２１】
デブリフィルタ３０は、例えば図３に示す構造であって、冷却材中に不可避的に混入した異物の燃料支持金具４０内部への侵入を阻止することができるものである。デブリフィルタ３０の各流路穴６３は例えば図３（ａ）に示すように千鳥格子状に配列され、各流路穴６３は図３（ｂ）に示すようにそれぞれが「く」の字状に曲がっている。なお、図３（ａ）ではフィルタ３０の全体形状がほぼ正方形で示されているが、図１、図２などに示す燃料支持金具４０の入口部におけるフィルタ３０の全体形状は通常は円形である。
【００２２】
図１は、本発明に係る燃料支持金具フィルタ検査装置の第１の実施の形態である圧損検査装置１０を燃料支持金具４０に取り付けた状態を示す。図示の状態は、原子炉が停止した定期検査のときであって、燃料支持金具４０の上の４個の燃料集合体（図示せず）はすべて炉外に取り出されている。燃料集合体が載置されていた４個の開口６０のうちの１個に圧損検査装置１０の整流管１１の下端が挿入されている。
【００２３】
圧損検査装置１０は、下部に鉛直方向に延びる整流管１１と、整流管１１の上方に連設されたベンチュリ管１２および水中ポンプ１３を有する。ベンチュリ管１２と水中ポンプ１３の間にサポート１４があって、サポート１４が原子炉の上部格子板５２で支持されている。
【００２４】
燃料支持金具４０は、制御棒案内管５１を介して炉心支持板５０に取り付けられている。圧損検査装置１０は全体が炉水中に浸かっている。また、検査は定期点検中に行なうため、炉水の流れはない。
【００２５】
以上の構成で、水中ポンプ１３を作動させると、炉水はデブリフィルタ３０を通過して燃料支持金具４０へ流れ込み、整流管１１およびベンチュリ管１２を通って水中ポンプ１３の吐出口から排出される。整流管１１に流れる流量は、ベンチュリ管１２の入口圧力測定点１２ａと出口圧力測定点１２ｂの差圧に基いて測定できる。これにより、所定の流量が流れるよう水中ポンプ１３を制御する。
【００２６】
デブリフィルタ３０の入口の圧力は水頭圧で一定であり、デブリフィルタ３０の出口の圧力は整流管１１の入口の圧力とほぼ同一であるから、整流管１１の入口部に圧力測定点１０ａを設けることによりデブリフィルタ３０の差圧を算出できる。したがって、定期点検ごとに所定流量における圧力測定点１０ａの圧力を測定することにより、デブリフィルタ３０の圧損増加（経年変化）を検出できる。
【００２７】
次に、本発明に係る燃料支持金具フィルタ検査装置の第２の実施の形態である目視検査装置２０を図４に基き説明する。目視検査装置２０は、水中カメラ２１および水中照明具２２を有する。
【００２８】
図４に示すように、水中カメラ２１は燃料支持金具４０の開口６０から内部に挿入し、デブリフィルタ３０を内側から見られる位置に設置する。また、燃料支持金具４０の外側で水中カメラ２１とは反対側の位置に水中照明具２２を設置し、デブリフィルタ３０の各流路穴６３を外側から照らす。これにより、「く」の字状に曲げられた流路穴６３の内部に光が投光され、反射光によって、反対側にある水中カメラ２１で目視可能となる。
【００２９】
また、水中カメラ２１と水中照明具２２の位置を入れ替えることにより、デブリフィルタ３０の両側を目視することができる（図示せず）。さらに、水中カメラ２１と水中照明具２２を接近させて横に同じ向きに並べてデブリフィルタ３０を目視することもできる（図示せず）。
【００３０】
【発明の効果】
以上説明したように、本発明によれば、原子炉の定期検査時などの運転停止時に燃料支持金具のフィルタの目詰まり状況などを検査することができる。
【図面の簡単な説明】
【図１】本発明に係る燃料支持金具フィルタ検査装置の第１の実施の形態であるデブリフィルタ圧損検査装置を燃料支持金具に取り付けた状態を示す図であって、（ａ）は全体立断面図、（ｂ）は（ａ）のＢ−Ｂ線矢視水平断面図。
【図２】沸騰水型原子炉のデブリフィルタ付き燃料支持金具を示す図であって、（ａ）は平面図、（ｂ）は（ａ）のＢ−Ｂ線矢視立断面図。
【図３】図２のデブリフィルタを取り出して示す図であって、（ａ）は正面図、（ｂ）は（ａ）のＢ−Ｂ線矢視側断面図。
【図４】本発明に係る燃料支持金具フィルタ検査装置の第２の実施の形態である目視検査装置を燃料支持金具とともに示す模式的立面図。
【符号の説明】
１０…圧損検査装置、１０ａ…圧力測定点、１１…整流管、１２…ベンチュリ管、１２ａ…ベンチュリ管入口圧力測定点、１２ｂ…ベンチュリ管出口圧力測定点、１３…水中ポンプ、１４…サポート、２０…目視検査装置、２１…水中カメラ、２２…水中照明具、３０…デブリフィルタ、４０…燃料支持金具、５０…炉心支持板、５１…制御棒案内管、５２…制御棒案内管、６０…開口、６１…制御棒穴、６３…流路穴。[0001]
TECHNICAL FIELD OF THE INVENTION
The present invention relates to an inspection device and an inspection method for inspecting a filter attached near a core inlet of a nuclear reactor when the reactor is stopped, such as during a periodic inspection.
[0002]
[Prior art]
Generally, there is a possibility that cladding contained in reactor water may adhere to the surface of equipment installed in a nuclear reactor. As a method of confirming the state of clad adhesion, a method is usually employed in which a submersible camera is put into reactor water during periodic inspections in which the reactor is stopped, and a corresponding portion is observed with a camera.
[0003]
Recently, it has been studied to attach a debris filter near the core inlet to capture solid foreign matter (debris) contained in the coolant before entering the core (for example, Japanese Patent Application Laid-Open No. Hei 7-253471). And JP-A-4-230892. However, there is no record of application to an actual operating plant, and a method of inspecting the state of clad adhesion due to aging and the effect of clad adhesion has not yet been established.
[0004]
[Problems to be solved by the invention]
However, the pressure loss (pressure loss) of the debris filter is an important factor that greatly affects the core flow rate. Therefore, it is necessary to quantitatively measure a change in pressure loss due to the adhesion of the clad. Further, in particular, when the hole of the debris filter is bent inside, only the surface can be visually observed only by looking at the camera, but the internal state cannot be seen. For this reason, it is not possible to confirm the state of clogging of the debris filter due to the captured debris.
[0005]
The present invention has been made in view of such a conventional situation. For a filter installed near the core inlet of an operating plant, during plant shutdown, clogging due to a change in pressure loss due to adhesion of cladding or debris. It is an object of the present invention to provide an apparatus and a method capable of checking a situation.
[0006]
[Means for Solving the Problems]
The present invention achieves at least a part of the above object, and the invention according to claim 1 supports a fuel assembly in a nuclear reactor and introduces water into the fuel assembly through a filter. From a fuel support fitting, when the operation of the nuclear reactor is stopped, the fuel assembly is removed underwater, and then attached to the fuel support fitting underwater to check the pressure loss of the filter. A pipe connected to the fuel support after removing the fuel assembly, a pump for driving a flow of water entering the pipe through the filter, and a flow meter for measuring a flow rate in the pipe, Pressure loss measuring means for measuring the pressure loss of the filter.
[0007]
According to the invention of claim 1, when the operation of the nuclear reactor is stopped, the pressure loss of the filter can be quantitatively measured in a state where the fuel support is installed in the reactor, and the secular change of the pressure loss due to the adhesion of the clad can be inspected. it can.
[0008]
According to a second aspect of the present invention, in the fuel support fitting filter inspection apparatus according to the first aspect, the flow meter uses a Venturi tube. According to the second aspect of the invention, the operation and effect of the first aspect of the invention can be obtained, and the flow rate in the pipe can be easily measured.
[0009]
According to a third aspect of the present invention, in the fuel support fitting filter inspection apparatus according to the first or second aspect, the pressure loss measuring means includes a means for measuring a pressure in the pipe. According to the third aspect of the invention, the operation and effect of the first or second aspect of the invention can be obtained, and the pressure loss of the filter can be easily measured.
[0010]
According to a fourth aspect of the present invention, there is provided a fuel support for inspecting a pressure loss of a filter attached to a fuel support for supporting a fuel assembly in a nuclear reactor and introducing water into the fuel assembly. In the filter inspection method, when the operation of the nuclear reactor is stopped, a removal step of removing the fuel assembly from the fuel support fitting in water, and a fuel support fitting filter pressure loss inspection device in water on the fuel support fitting after the removal step. Attachment attaching step, after the attaching step, a flow step of driving a pump of the fuel support fitting filter pressure loss inspection device to create a flow of water through the filter, and a flow rate of water passing through the filter in the flowing step and And measuring a pressure loss in the filter.
[0011]
According to the invention of claim 4, when the operation of the nuclear reactor is stopped, the pressure loss of the filter can be quantitatively measured in a state where the fuel support fitting is installed in the reactor, and the secular change of the pressure loss due to the adhesion of the clad or the like is inspected. be able to.
[0012]
Further, the invention according to claim 5 is characterized in that the fuel assembly is supported in a nuclear reactor, and a fuel support fitting for introducing water into the fuel assembly through a filter is provided when the operation of the nuclear reactor is stopped. A fuel support fitting filter inspection device for visually observing the filter underwater from inside and outside of the fuel support after removing the assembly, wherein the filter is provided underwater and from inside and outside of the fuel support. And a lighting device that can be brought close to the camera.
[0013]
According to the invention of claim 5, when the operation of the nuclear reactor is stopped, the condition of the flow passage hole of the filter can be visually observed while brightly illuminating the condition of the flow passage hole in a state where the fuel support fitting is installed in the reactor.
[0014]
According to a sixth aspect of the present invention, in the fuel support fitting filter inspection apparatus according to the fifth aspect, the camera and the lighting fixture are arranged so as to face each other with the filter interposed therebetween. It is characterized by. According to the sixth aspect of the invention, the operation and effect of the fifth aspect of the invention can be obtained, and the inside of the flow path hole of the filter can be clearly visually observed by light from the back surface.
[0015]
According to a seventh aspect of the present invention, there is provided a fuel support filter inspection method for supporting a fuel assembly in a nuclear reactor and for inspecting a filter attached to the fuel support for introducing water into the fuel assembly. In the reactor, when the operation of the reactor is stopped, a removing step of removing the fuel assembly from the fuel support fitting in water, and after the removing step, a camera and a lighting fixture are brought close to the filter in water and the filter is visually observed. And an observation step of observing.
[0016]
According to the invention of claim 7, when the operation of the nuclear reactor is stopped, the condition of the flow passage hole of the filter can be visually observed while the fuel support fitting is installed in the reactor while brightly illuminating the condition.
[0017]
According to an eighth aspect of the present invention, in the fuel support fitting filter inspection method according to the seventh aspect, the observation step is performed in a state where the camera and the lighting fixture are arranged to face each other with the filter interposed therebetween. It is characterized by the following. According to the eighth aspect of the invention, the operation and effect of the seventh aspect of the invention can be obtained, and the inside of the flow path hole of the filter can be clearly visually observed by light from the back surface.
[0018]
BEST MODE FOR CARRYING OUT THE INVENTION
Hereinafter, embodiments of a fuel support fitting filter inspection apparatus and an inspection method according to the present invention will be described with reference to the drawings. Here, common or similar parts are denoted by common reference numerals, and redundant description will be appropriately omitted.
[0019]
First, a first embodiment of a fuel support fitting filter inspection apparatus according to the present invention will be described with reference to FIGS.
FIG. 2 shows a fuel support fitting 40 of the boiling water reactor. As shown, there are four openings 60 in the upper part, and a fuel assembly (not shown) is mounted on each of them. A coolant flow path is formed in the fuel support fitting 40 toward each opening 60, and the inlet of the fuel support fitting 40 is open outward in the horizontal direction, and the debris filter 30 is attached to each inlet. I have. A control rod hole 61 having a cruciform horizontal cross section is formed at the center of the fuel support fitting 40 so that a control rod (not shown) having a cruciform horizontal cross section can penetrate in the vertical direction.
[0020]
As shown in FIG. 1, the fuel support fitting 40 is partially supported by a hole provided in the core support plate 50. Further, a control rod guide tube 52 is disposed directly below the fuel support fitting 40. Although FIG. 1 shows only one fuel support member 40 and one control rod guide tube 52, a plurality of these are arranged in a grid in the horizontal direction.
[0021]
The debris filter 30 has, for example, the structure shown in FIG. 3 and can prevent foreign substances unavoidably mixed in the coolant from entering the fuel support fitting 40. Each of the passage holes 63 of the debris filter 30 is arranged in a staggered pattern as shown in FIG. 3A, for example, and each of the passage holes 63 is shaped like a “C” as shown in FIG. 3B. It is bent. Although the overall shape of the filter 30 is shown in FIG. 3A as a substantially square, the overall shape of the filter 30 at the inlet of the fuel support fitting 40 shown in FIGS. .
[0022]
FIG. 1 shows a state in which a pressure drop inspection device 10 as a first embodiment of a fuel support fitting filter inspection apparatus according to the present invention is attached to a fuel support fitting 40. The state shown is the time of a periodic inspection in which the nuclear reactor is shut down, and all four fuel assemblies (not shown) on the fuel support fitting 40 have been taken out of the reactor. The lower end of the flow straightening tube 11 of the pressure loss inspection device 10 is inserted into one of the four openings 60 in which the fuel assembly is placed.
[0023]
The pressure loss inspection device 10 includes a straightening pipe 11 extending vertically in a lower part, a venturi pipe 12 and a submersible pump 13 connected continuously above the straightening pipe 11. There is a support 14 between the Venturi tube 12 and the submersible pump 13, and the support 14 is supported by the upper lattice plate 52 of the reactor.
[0024]
The fuel support fitting 40 is attached to the core support plate 50 via a control rod guide tube 51. The entire pressure drop inspection device 10 is immersed in the furnace water. In addition, there is no flow of reactor water because the inspection is performed during the periodic inspection.
[0025]
With the above configuration, when the submersible pump 13 is operated, the reactor water flows through the debris filter 30, flows into the fuel support fitting 40, and is discharged from the discharge port of the submersible pump 13 through the rectifying pipe 11 and the venturi pipe 12. . The flow rate flowing through the straightening pipe 11 can be measured based on the pressure difference between the inlet pressure measuring point 12a and the outlet pressure measuring point 12b of the Venturi pipe 12. Thereby, the submersible pump 13 is controlled so that a predetermined flow rate flows.
[0026]
Since the pressure at the inlet of the debris filter 30 is constant at the head pressure and the pressure at the outlet of the debris filter 30 is almost the same as the pressure at the inlet of the rectifier tube 11, a pressure measurement point 10a is provided at the inlet of the rectifier tube 11. Thus, the differential pressure of the debris filter 30 can be calculated. Therefore, by measuring the pressure at the pressure measurement point 10a at the predetermined flow rate at each periodic inspection, it is possible to detect an increase in pressure loss (deterioration over time) of the debris filter 30.
[0027]
Next, a visual inspection device 20, which is a second embodiment of the fuel support fitting filter inspection device according to the present invention, will be described with reference to FIG. The visual inspection device 20 has an underwater camera 21 and an underwater lighting device 22.
[0028]
As shown in FIG. 4, the underwater camera 21 is inserted into the fuel support fitting 40 through the opening 60, and the debris filter 30 is installed at a position that can be seen from the inside. Further, the underwater lighting fixture 22 is installed at a position outside the fuel support fitting 40 and on the side opposite to the underwater camera 21, and illuminates the respective channel holes 63 of the debris filter 30 from outside. Thereby, light is projected inside the channel hole 63 bent in the shape of a “<”, and the reflected light makes it visible with the underwater camera 21 on the opposite side.
[0029]
In addition, by swapping the positions of the underwater camera 21 and the underwater lighting fixture 22, both sides of the debris filter 30 can be visually checked (not shown). Furthermore, the underwater camera 21 and the underwater lighting fixture 22 can be arranged close to each other in the same direction and the debris filter 30 can be visually checked (not shown).
[0030]
【The invention's effect】
As described above, according to the present invention, it is possible to inspect the clogging state of the filter of the fuel support bracket when the operation is stopped, such as during the periodic inspection of the nuclear reactor.
[Brief description of the drawings]
FIG. 1 is a diagram showing a state in which a debris filter pressure loss inspection device, which is a first embodiment of a fuel support fitting filter inspection apparatus according to the present invention, is attached to a fuel support fitting; FIG. FIG. 2B is a horizontal sectional view taken along line BB of FIG.
FIGS. 2A and 2B are diagrams showing a fuel support fitting with a debris filter of a boiling water reactor, wherein FIG. 2A is a plan view and FIG. 2B is a vertical sectional view taken along line BB of FIG.
FIGS. 3A and 3B are diagrams showing the debris filter of FIG. 2 taken out, in which FIG. 3A is a front view, and FIG. 3B is a sectional view taken along line BB of FIG.
FIG. 4 is a schematic elevation view showing a visual inspection device, which is a second embodiment of the fuel support fitting filter inspection apparatus according to the present invention, together with the fuel support fitting.
[Explanation of symbols]
DESCRIPTION OF SYMBOLS 10 ... Pressure loss inspection apparatus, 10a ... Pressure measuring point, 11 ... Rectifier pipe, 12 ... Venturi pipe, 12a ... Venturi pipe inlet pressure measuring point, 12b ... Venturi pipe outlet pressure measuring point, 13 ... Submersible pump, 14 ... Support, 20 ... visual inspection device, 21 ... underwater camera, 22 ... underwater lighting device, 30 ... debris filter, 40 ... fuel support bracket, 50 ... core support plate, 51 ... control rod guide tube, 52 ... control rod guide tube, 60 ... opening , 61: control rod hole, 63: channel hole.

Claims (8)

原子炉内で燃料集合体を支持し、フィルタを通して前記燃料集合体に水を導入するための燃料支持金具から、前記原子炉の運転停止時に、前記燃料集合体を水中で外したあとにその燃料支持金具に水中で取り付けられて、前記フィルタの圧力損失を検査する燃料支持金具フィルタ検査装置において、
前記燃料集合体を外したあとの前記燃料支持金具に接続される管と、前記フィルタを通って前記管に入る水の流れを駆動するポンプと、前記管内の流量を測定する流量計と、前記フィルタの圧力損失を測定する圧損測定手段と、を有することを特徴とする燃料支持金具フィルタ検査装置。The fuel assembly is supported in the reactor, and the fuel assembly is removed from the fuel support fitting for introducing water into the fuel assembly through a filter. In a fuel support fitting filter inspection device that is attached to a support fitting in water and checks the pressure loss of the filter,
A pipe connected to the fuel support after removing the fuel assembly, a pump for driving a flow of water entering the pipe through the filter, a flow meter for measuring a flow rate in the pipe, A fuel support fitting filter inspection device, comprising: a pressure loss measuring means for measuring a pressure loss of a filter. 請求項１に記載の燃料支持金具フィルタ検査装置において、前記流量計はベンチュリ管を用いるものであること、を特徴とする燃料支持金具フィルタ検査装置。2. The fuel support fitting filter inspection apparatus according to claim 1, wherein the flow meter uses a Venturi tube. 請求項１または２に記載の燃料支持金具フィルタ検査装置において、前記圧損測定手段は、前記管内の圧力を測定する手段を含むこと、を特徴とする燃料支持金具フィルタ検査装置。3. The fuel support fitting filter inspection apparatus according to claim 1, wherein the pressure loss measuring means includes a means for measuring a pressure in the pipe. 原子炉内で燃料集合体を支持して前記燃料集合体に水を導入するための燃料支持金具に取り付けられたフィルタの圧力損失を検査する燃料支持金具フィルタ検査方法において、
前記原子炉の運転停止時に、水中で前記燃料支持金具から前記燃料集合体を外す取り外し工程と、
前記取り外し工程の後に前記燃料支持金具に水中で燃料支持金具フィルタ圧損検査装置を取り付ける取り付け工程と、
前記取り付け工程の後に、前記燃料支持金具フィルタ圧損検査装置のポンプを駆動して前記フィルタを通る水の流れを作る流動工程と、
前記流動工程における前記フィルタを通る水の流量および前記フィルタでの圧力損失を測定する測定工程と、
を有することを特徴とする燃料支持金具フィルタ検査方法。A fuel support fitting filter testing method for testing a pressure loss of a filter attached to a fuel support fitting for supporting a fuel assembly in a nuclear reactor and introducing water into the fuel assembly,
When the operation of the reactor is stopped, a removal step of removing the fuel assembly from the fuel support fitting in water,
Attachment step of attaching a fuel support fitting filter pressure loss inspection device in water to the fuel support fitting after the removing step,
After the attaching step, a flow step of driving a pump of the fuel support fitting filter pressure loss inspection device to create a flow of water through the filter,
A measurement step of measuring a flow rate of water passing through the filter and a pressure loss at the filter in the flow step,
A fuel support fitting filter inspection method, comprising: 原子炉内で燃料集合体を支持し、フィルタを通して前記燃料集合体に水を導入するための燃料支持金具から、前記原子炉の運転停止時に、前記燃料集合体を外したあとにその燃料支持金具の内側および外側から前記フィルタを水中で目視観察するための燃料支持金具フィルタ検査装置であって、
水中で、前記燃料支持金具の内側および外側から前記フィルタに近づけることのできるカメラおよび照明具を有すること、を特徴とする燃料支持金具フィルタ検査装置。A fuel support for supporting a fuel assembly in a nuclear reactor and for removing water from the fuel support for introducing water into the fuel assembly through a filter during shutdown of the reactor after removing the fuel assembly. A fuel support fitting filter inspection device for visually observing the filter in water from inside and outside of the filter,
A fuel support fitting filter inspection apparatus, comprising: a camera and a lighting device that can approach the filter from inside and outside of the fuel support fitting in water. 請求項５に記載の燃料支持金具フィルタ検査装置において、前記カメラと照明具が前記フィルタをはさんで向かい合って配置されるように構成されていること、を特徴とする燃料支持金具フィルタ検査装置。The fuel support fitting filter inspection device according to claim 5, wherein the camera and the lighting device are arranged so as to face each other with the filter interposed therebetween. 原子炉内で燃料集合体を支持して前記燃料集合体に水を導入するための燃料支持金具に取り付けられたフィルタを検査する燃料支持金具フィルタ検査方法において、
前記原子炉の運転停止時に、水中で前記燃料支持金具から前記燃料集合体を外す取り外し工程と、
前記取り外し工程の後に、水中で、カメラおよび照明具を前記フィルタに近づけて当該フィルタを目視観測する観測工程と、
を有することを特徴とする燃料支持金具フィルタ検査方法。A fuel support fitting filter testing method for testing a filter attached to a fuel support fitting for supporting a fuel assembly in a nuclear reactor and introducing water into the fuel assembly,
When the operation of the reactor is stopped, a removal step of removing the fuel assembly from the fuel support fitting in water,
After the removal step, in water, an observation step of visually observing the filter by bringing a camera and a lighting tool close to the filter,
A fuel support fitting filter inspection method, comprising: 請求項７に記載の燃料支持金具フィルタ検査方法において、前記観測工程は、前記カメラと照明具が前記フィルタをはさんで向かい合って配置した状態で行なわれること、を特徴とする燃料支持金具フィルタ検査方法。8. The fuel support fitting filter inspection method according to claim 7, wherein the observation step is performed in a state where the camera and the lighting fixture are arranged to face each other with the filter interposed therebetween. Method.
JP2002176610A 2002-06-18 2002-06-18 Fuel support fitting filter inspection device and inspection method Expired - Fee Related JP3944004B2 (en)

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Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN104888680A (en) * 2015-05-13 2015-09-09 成都佳美嘉科技有限公司 Distillation reactor

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN104888680A (en) * 2015-05-13 2015-09-09 成都佳美嘉科技有限公司 Distillation reactor

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