JP2018091710A - Reactor water level detection device and nuclear reactor - Google Patents

Reactor water level detection device and nuclear reactor Download PDF

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JP2018091710A
JP2018091710A JP2016235028A JP2016235028A JP2018091710A JP 2018091710 A JP2018091710 A JP 2018091710A JP 2016235028 A JP2016235028 A JP 2016235028A JP 2016235028 A JP2016235028 A JP 2016235028A JP 2018091710 A JP2018091710 A JP 2018091710A
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reactor
water level
detection device
level detection
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JP6767850B2 (en
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慎二郎 猪又
Shinjiro Inomata
慎二郎 猪又
和生 曽我
Kazuo Soga
和生 曽我
雄一 最上
Yuichi Mogami
雄一 最上
松原 亨
Toru Matsubara
亨 松原
一寿 青柳
Kazuhisa Aoyagi
一寿 青柳
聡志 米元
Satoshi Yonemoto
聡志 米元
堀川 好一
Koichi Horikawa
好一 堀川
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Mitsubishi Heavy Industries Ltd
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Abstract

PROBLEM TO BE SOLVED: To provide a reactor water level detection device and a nuclear reactor which improve workability of maintenance work on the nuclear reactor.SOLUTION: A reactor water level detection device includes: a water level gauge 41 for detecting a water level of a primary coolant; and a storage pipe 42 for storing the water level gauge 41. In the storage pipe 42, a lower part is supported by a support pipe 61 fixed to an upper core plate 20, and an upper part is supported detachably from a nozzle stub 62 of a reactor vessel lid 13 by a clip 66.SELECTED DRAWING: Figure 1

Description

本発明は、原子炉内における冷却材の水位を検出するための原子炉水位検出装置、この原子炉水位検出装置が装着された原子炉に関するものである。   The present invention relates to a reactor water level detection device for detecting the coolant level in a nuclear reactor, and a reactor equipped with the reactor water level detection device.

例えば、原子力発電プラントにて、加圧水型原子炉は、軽水を原子炉冷却材及び中性子減速材として使用し、炉心全体にわたって沸騰しない高温高圧水とし、この高温高圧水を蒸気発生器に送って給水と熱交換することで蒸気を生成するものであり、この蒸気をタービン発電機へ送って発電することができる。   For example, in a nuclear power plant, a pressurized water reactor uses light water as a reactor coolant and a neutron moderator, turns it into high-temperature and high-pressure water that does not boil throughout the core, and sends this high-temperature and high-pressure water to a steam generator to supply water. The steam is generated by exchanging heat with the steam, and the steam can be sent to a turbine generator to generate power.

この加圧水型原子炉は、原子炉容器内に炉心が設けられており、この炉心は、多数の燃料集合体により構成されており、この燃料集合体に対して制御棒クラスタを挿入することで、原子炉の出力を制御可能となっている。冷却材(軽水)は、入口ノズルから原子炉容器内に供給された後、下降して底部で反転し、燃料集合体に沿って上昇するときに燃料を冷却することで加熱され、出口ノズルから排出されて蒸気発生器に送られる。また、加圧水型原子炉は、原子炉容器内に冷却材の水位を検出する水位検出装置が設けられている。   In this pressurized water reactor, a core is provided in a reactor vessel, and this core is composed of a large number of fuel assemblies. By inserting control rod clusters into the fuel assemblies, The reactor power can be controlled. After the coolant (light water) is supplied into the reactor vessel from the inlet nozzle, it descends, reverses at the bottom, and is heated by cooling the fuel as it rises along the fuel assembly. It is discharged and sent to a steam generator. Further, the pressurized water reactor is provided with a water level detection device for detecting the coolant level in the reactor vessel.

原子炉容器内における冷却材の水位を検出する水位検出装置としては、例えば、下記特許文献に記載されたものがある。各特許文献に記載された水位検出装置は、中間部が上部炉心支持板に支持され、下部が上部炉心板に支持され、上部が原子炉容器蓋に支持されている。   As a water level detection device for detecting the water level of the coolant in the reactor vessel, for example, there is one described in the following patent document. In each of the water level detection devices described in each patent document, an intermediate portion is supported by an upper core support plate, a lower portion is supported by an upper core plate, and an upper portion is supported by a reactor vessel lid.

実公平03−001768号公報No. 03-001768 特開平08−220284号公報Japanese Patent Laid-Open No. 08-220284

ところで、原子炉をメンテナンスするとき、原子炉容器本体に対して原子炉容器蓋を取り外した後、炉内構造物の取り出しや燃料集合体の交換などの作業を実施する。水位検出装置は、一般的に、収納部材内に水位計が挿入されて構成されている。収納部材は、一方が炉内構造物側に設置された支持部材に支持され、他方が原子炉容器蓋に固定されている。水位計は、原子炉容器本体内部の冷却材の水位を計測するため、一般に、水位計の全長は、原子炉容器蓋の全長よりも長くなる。そのため、原子炉のメンテナンスにおいて、水位計を収納部材に挿入した状態で、原子炉容器に対して原子炉容器蓋を取り外すと、原子炉容器蓋を移動あるいは保管する際に、収納部材内部に挿入された水位計が、原子炉容器本体の周辺に設置された設備や機器、あるいはメンテナンスに係る作業者に接触するといったおそれがあるため、原子炉をメンテナンスする際には、水位計を収納部材から引き抜く作業が必要となる。メンテナンス完了後には、水位計を収納部材に再度挿入する作業が必要となる。この水位計を収納部材から引き抜く、或いは水位計を収納部材に挿入する作業は、原子炉のメンテナンスに際して常に必要となる作業であり、原子炉のメンテナンス期間が長くなる、且つ作業者の被曝量が増加するという課題となっている。   By the way, when maintaining the nuclear reactor, after removing the reactor vessel lid from the reactor vessel main body, operations such as taking out the reactor internal structure and replacing the fuel assembly are performed. The water level detection device is generally configured by inserting a water level meter into a storage member. One of the storage members is supported by a support member installed on the reactor internal structure side, and the other is fixed to the reactor vessel lid. Since the water level gauge measures the water level of the coolant inside the reactor vessel main body, the total length of the water level meter is generally longer than the total length of the reactor vessel lid. Therefore, when the reactor vessel lid is removed from the reactor vessel with the water level gauge inserted into the storage member during maintenance of the reactor, it is inserted into the storage member when the reactor vessel lid is moved or stored. The water level gauge may come into contact with equipment or equipment installed around the reactor vessel body or maintenance personnel. Pulling out work is required. After the maintenance is completed, it is necessary to reinsert the water level meter into the storage member. The operation of pulling out the water level meter from the storage member or inserting the water level meter into the storage member is an operation that is always necessary for maintenance of the reactor, which increases the maintenance period of the reactor and increases the exposure amount of the operator. It is a problem of increasing.

本発明は、上述した課題を解決するものであり、原子炉のメンテナンス作業の作業性の向上を図る原子炉水位検出装置及び原子炉を提供することを目的とする。   The present invention solves the above-described problems, and an object of the present invention is to provide a reactor water level detection device and a reactor that improve the workability of the maintenance work of the reactor.

上記の目的を達成するための本発明の原子炉水位検出装置は、冷却材の水位を検出する水位計と、前記水位計を収納する収納部材と、を備え、前記収納部材は、下部が炉内構造物側に設けられる支持部材に支持される一方、上部が原子炉容器蓋に対して着脱自在に支持される、ことを特徴とするものである。   In order to achieve the above object, a reactor water level detection device according to the present invention includes a water level meter for detecting the water level of a coolant and a storage member for storing the water level meter. While being supported by a support member provided on the inner structure side, the upper part is detachably supported with respect to the reactor vessel lid.

従って、収納部材の下部が炉内構造物側に設けられる支持部材に支持される一方、上部が原子炉容器蓋に着脱自在に支持されることで、原子炉のメンテナンス時に、原子炉容器本体から原子炉容器蓋を取り外したとき、水位計が収納された収納部材が原子炉容器蓋から分離されることから、水位計を収納部材から引き抜く、または、水位計を収納部材に挿入するといった作業が不要となる。そのため、原子炉のメンテナンスに係る作業時間が短縮されると共に作業者の被曝量も低減され、原子炉のメンテナンス作業の作業性の向上を図ることができる。   Therefore, while the lower part of the storage member is supported by the support member provided on the reactor internal structure side, the upper part is detachably supported by the reactor vessel lid, so that the reactor vessel main body can be removed during the maintenance of the reactor. When the reactor vessel lid is removed, the storage member in which the water level gauge is stored is separated from the reactor vessel lid, so that the operation of pulling out the water level meter from the storage member or inserting the water level meter into the storage member is performed. It becomes unnecessary. Therefore, the work time for the maintenance of the reactor is shortened and the exposure amount of the worker is also reduced, so that the workability of the maintenance work of the reactor can be improved.

本発明の原子炉水位検出装置では、前記原子炉容器蓋に管台が固定され、前記収納部材は、上端部が前記管台を貫通し、係止部材により着脱自在に係止されることを特徴としている。   In the reactor water level detection device of the present invention, a nozzle is fixed to the reactor vessel lid, and the storage member has an upper end penetrating the nozzle and is detachably locked by a locking member. It is a feature.

従って、係止部材を操作するだけで、原子炉容器蓋の管台に対して収納部材が着脱自在となり、原子炉容器本体に対して原子炉容器蓋を昇降させるだけで、原子炉容器蓋を収納部材から分離、または、原子炉容器蓋を収納部材に装着することができる。   Accordingly, the storage member can be freely attached to and detached from the reactor vessel lid nozzle simply by operating the locking member, and the reactor vessel lid can be removed by simply raising and lowering the reactor vessel lid with respect to the reactor vessel body. The reactor vessel lid can be attached to the storage member or separated from the storage member.

本発明の原子炉水位検出装置では、前記収納部材は、本体部と上小径部とが設けられ、前記本体部と前記上小径部との間に段付き部が設けられ、前記段付き部と前記管台との間にシール部材が介装されることを特徴としている。   In the reactor water level detection device of the present invention, the storage member is provided with a main body portion and an upper small diameter portion, and a stepped portion is provided between the main body portion and the upper small diameter portion. A seal member is interposed between the nozzle and the nozzle.

従って、収納部材の段付き部と管台とを互いに接近する方向に移動するだけで、シール部材を収納部材と管台に密着させ、この密着状態で係止部材により収納部材を係止すればよく、シール性及びシール装着性を向上することができる。   Therefore, the seal member is brought into close contact with the storage member and the nozzle by simply moving the stepped portion of the storage member and the nozzle close to each other, and the storage member is locked by the locking member in this tight contact state. It is possible to improve the sealing performance and the seal mounting performance.

本発明の原子炉水位検出装置では、前記炉内構造物に支持部材が固定され、前記収納部材は、下端部が前記支持部材により長手方向に沿って移動自在に支持されると共に、付勢部材により前記シール部材が押圧される方向に付勢支持されることを特徴としている。   In the reactor water level detection device of the present invention, a support member is fixed to the reactor internal structure, and the storage member is supported by the support member so as to be movable along the longitudinal direction, and the biasing member. Thus, the seal member is biased and supported in the pressing direction.

従って、管台に対して収納部材を上方に移動させることで、シール部材を収納部材と管台に密着させることができ、この密着状態で係止部材により収納部材を係止すればよい。また、係止部材を取り外して収納部材の係止状態を解除すると、収納部材が自重により下降するが、収納部材は付勢部材の付勢力により支持されることから、炉内構造物への衝突が防止され、収納部材の損傷を防止することができる。   Therefore, by moving the storage member upward with respect to the nozzle, the seal member can be brought into close contact with the storage member and the nozzle, and the storage member may be locked by the locking member in this close contact state. Moreover, when the latching member is removed and the latching state of the storage member is released, the storage member descends due to its own weight, but the storage member is supported by the biasing force of the biasing member, so that it collides with the reactor internal structure. Is prevented, and damage to the storage member can be prevented.

本発明の原子炉水位検出装置では、前記収納部材は、前記付勢部材の付勢力により下端部が前記炉内構造物から離間して支持されることを特徴としている。   In the nuclear reactor water level detection apparatus according to the present invention, the storage member is supported by the lower end portion thereof being separated from the reactor internal structure by the biasing force of the biasing member.

従って、管台に対して収納部材の移動量を確保してシール部材の装着性を向上することができると共に、収納部材の下降時の衝撃を付勢部材により緩和して収納部材の損傷を防止することができる。   Therefore, the amount of movement of the storage member relative to the nozzle can be secured to improve the mounting performance of the seal member, and the impact when the storage member is lowered is reduced by the biasing member to prevent the storage member from being damaged. can do.

本発明の原子炉水位検出装置では、前記支持部材は、筒形状をなし、前記収納部材は、下端部が前記支持部材内に配置され、前記支持部材と前記収納部材との間に前記収納部材を位置決め保持する位置決め部材が設けられることを特徴としている。   In the reactor water level detection device of the present invention, the support member has a cylindrical shape, and the storage member has a lower end disposed in the support member, and the storage member is interposed between the support member and the storage member. It is characterized in that a positioning member for positioning and holding is provided.

従って、収納部材は、位置決め部材を介して支持部材に支持されることから、収納部材が炉内構造物に対して所定の位置に安定して支持されることとなり、原子炉容器蓋を容易に原子炉容器本体に取付けることができる。   Accordingly, since the storage member is supported by the support member via the positioning member, the storage member is stably supported at a predetermined position with respect to the reactor internal structure, and the reactor vessel lid can be easily secured. It can be attached to the reactor vessel body.

また、本発明の原子炉は、前記原子炉水位検出装置が設けられることを特徴とするものである。   Moreover, the nuclear reactor of the present invention is characterized in that the reactor water level detection device is provided.

従って、原子炉容器内の水位を高精度に検出することができると共に、原子炉のメンテナンス作業の作業性の向上を図ることができる。   Therefore, the water level in the reactor vessel can be detected with high accuracy, and the workability of the maintenance work of the reactor can be improved.

本発明の原子炉水位検出装置及び原子炉によれば、水位計を収納する収納部材の下部を炉内構造物に支持し、上部を原子炉容器蓋に対して着脱自在に支持するので、原子炉のメンテナンス作業の作業性の向上を図ることができる。   According to the reactor water level detection device and the reactor of the present invention, the lower part of the storage member for storing the water level gauge is supported by the reactor internal structure, and the upper part is detachably supported by the reactor vessel lid. The workability of the furnace maintenance work can be improved.

図1は、本実施形態の原子炉水位検出装置を表す断面図である。FIG. 1 is a cross-sectional view showing a reactor water level detection device of the present embodiment. 図2は、加圧水型原子炉を表す縦断面図である。FIG. 2 is a longitudinal sectional view showing a pressurized water reactor.

以下に添付図面を参照して、本発明に係る原子炉水位検出装置及び原子炉の好適な実施形態を詳細に説明する。なお、この実施形態により本発明が限定されるものではなく、また、実施形態が複数ある場合には、各実施形態を組み合わせて構成するものも含むものである。   Exemplary embodiments of a reactor water level detection device and a reactor according to the present invention will be described below in detail with reference to the accompanying drawings. In addition, this invention is not limited by this embodiment, and when there are two or more embodiments, what comprises combining each embodiment is also included.

原子力発電プラントは、図示しないが、原子炉格納容器内に配置される原子炉及び蒸気発生器と、蒸気タービン発電設備とを有している。本実施形態の原子炉は、軽水を原子炉冷却材及び中性子減速材として使用し、炉心全体にわたって沸騰しない高温高圧水とし、この高温高圧水を蒸気発生器に送って熱交換により蒸気を発生させ、この蒸気をタービン発電機へ送って発電する加圧水型原子炉(PWR:Pressurized Water Reactor)である。   Although not shown, the nuclear power plant has a reactor and a steam generator disposed in the reactor containment vessel, and a steam turbine power generation facility. The nuclear reactor of the present embodiment uses light water as a reactor coolant and a neutron moderator, and produces high-temperature and high-pressure water that does not boil over the entire core, and sends this high-temperature and high-pressure water to a steam generator to generate steam by heat exchange. This is a pressurized water reactor (PWR) that generates electricity by sending this steam to a turbine generator.

図2は、加圧水型原子炉を表す縦断面図である。   FIG. 2 is a longitudinal sectional view showing a pressurized water reactor.

図2に示すように、加圧水型原子炉10において、原子炉容器11は、その内部に炉内構造物が挿入できるように、原子炉容器本体12とその上部に装着される原子炉容器蓋13により構成されており、この原子炉容器本体12に対して原子炉容器蓋13が複数のスタッドボルト14及びナット15により開閉可能に固定されている。   As shown in FIG. 2, in the pressurized water reactor 10, the reactor vessel 11 has a reactor vessel main body 12 and a reactor vessel lid 13 attached to the upper portion thereof so that the reactor internal structure can be inserted therein. The reactor vessel lid 13 is fixed to the reactor vessel body 12 by a plurality of stud bolts 14 and nuts 15 so as to be opened and closed.

原子炉容器本体12は、上部が開口し、下部が半球形状をなして閉塞された円筒形状をなしており、上部に一次冷却水(冷却材)としての軽水を供給する入口ノズル16と、軽水を排出する出口ノズル17が形成されている。原子炉容器本体12は、内部に炉心槽18が配置され、上部が原子炉容器本体12の内壁面に支持されている。上部炉心支持板19は、原子炉容器本体12の内部に配置され、上部が炉心槽18の上部に支持されている。上部炉心板20は、複数の炉心支持ロッド21により上部炉心支持板19に吊下げ支持されている。   The reactor vessel main body 12 has a cylindrical shape with an upper part opened and a lower part closed in a hemispherical shape. An inlet nozzle 16 for supplying light water as primary cooling water (coolant) to the upper part, and light water An outlet nozzle 17 for discharging the gas is formed. The reactor vessel body 12 has a reactor core 18 disposed therein, and an upper portion thereof is supported by the inner wall surface of the reactor vessel body 12. The upper core support plate 19 is disposed inside the reactor vessel main body 12, and the upper portion is supported by the upper portion of the core tank 18. The upper core plate 20 is suspended and supported on the upper core support plate 19 by a plurality of core support rods 21.

炉心槽18は、下方に下部炉心支持板22が支持され、下部炉心支持板22は、外周部が位置決め部材23により原子炉容器本体12の内壁面に位置決め支持されている。炉心槽18は、下部に下部炉心板24が支持されている。炉心25は、多数の燃料集合体26が配置されて構成されており、内部に多数の制御棒27が配置され、この制御棒27は、燃料集合体26に挿入可能となっている。上部炉心支持板19は、多数の制御棒クラスタ案内管28が固定され、内部に制御棒27が挿通可能となっている。原子炉容器蓋13は、半球形状をなし、制御棒駆動装置29が配置され、複数の制御棒クラスタ駆動軸30が制御棒クラスタ案内管28内に挿通され、下端部に制御棒27が連結されている。制御棒駆動装置29は、各制御棒27を炉心25に対して抜き差しすることで、原子炉出力を制御する。   A lower core support plate 22 is supported below the reactor core 18, and the outer periphery of the lower core support plate 22 is positioned and supported on the inner wall surface of the reactor vessel body 12 by a positioning member 23. The core tank 18 has a lower core plate 24 supported at the bottom. The core 25 is configured with a large number of fuel assemblies 26 disposed therein, and a large number of control rods 27 are disposed therein. The control rods 27 can be inserted into the fuel assemblies 26. A number of control rod cluster guide tubes 28 are fixed to the upper core support plate 19, and control rods 27 can be inserted therein. The reactor vessel lid 13 has a hemispherical shape, a control rod drive device 29 is disposed, a plurality of control rod cluster drive shafts 30 are inserted into the control rod cluster guide tube 28, and a control rod 27 is connected to the lower end portion. ing. The control rod drive device 29 controls the reactor power by inserting / removing each control rod 27 to / from the core 25.

そして、原子炉容器11は、原子炉容器11内の軽水(一次冷却材)の水位を検出する水位検出装置(原子炉水位検出装置)40が配置されている。水位検出装置40は、炉内構造物としての上部炉心支持板19を貫通して上部炉心板20に支持されており、原子炉容器蓋13に対して着脱自在となっている。   The reactor vessel 11 is provided with a water level detection device (reactor water level detection device) 40 that detects the level of light water (primary coolant) in the reactor vessel 11. The water level detection device 40 penetrates through the upper core support plate 19 as an in-reactor structure and is supported by the upper core plate 20 and is detachable from the reactor vessel lid 13.

図1は、本実施形態の原子炉水位検出装置を表す断面図である。   FIG. 1 is a cross-sectional view showing a reactor water level detection device of the present embodiment.

水位検出装置40は、図1に示すように、一次冷却材の水位を検出する水位計41と、水位計41を収納する収納管(収納部材)42とを備えている。   As shown in FIG. 1, the water level detection device 40 includes a water level meter 41 that detects the water level of the primary coolant, and a storage pipe (storage member) 42 that stores the water level meter 41.

水位計41は、例えば、加熱型熱電対式と一般に称されるものである。水位計41は、図示しないが、長さの異なる複数の熱電対から構成され、複数の熱電対は、原子炉容器11内に貯留されている一次冷却水における異なる高さでの冷却水温度を計測することができる。そして、原子炉容器11内に十分な量の一次冷却水が満たされているとき、各熱電対はほぼ同じ冷却水温度を計測し、温度差が実質的になく、水位計41は、原子炉容器11内に水が存在すると判定する。一方、原子炉容器11内一次冷却水が減少すると、一次冷却水から露出した熱電対の温度が上昇するため、各熱電対は異なる冷却水温度を計測し、温度差が発生し、水位計41は、原子炉容器11内の水が減少していると判定する。なお、水位計41として加熱型熱電対式を適用して説明したが、この方式に限定されるものではない。   The water level meter 41 is generally called, for example, a heating type thermocouple type. Although not shown in the drawing, the water level meter 41 is composed of a plurality of thermocouples having different lengths, and the plurality of thermocouples indicate the coolant temperature at different heights in the primary coolant stored in the reactor vessel 11. It can be measured. When a sufficient amount of primary cooling water is filled in the reactor vessel 11, each thermocouple measures substantially the same cooling water temperature, and there is substantially no temperature difference. It is determined that water is present in the container 11. On the other hand, when the primary cooling water in the reactor vessel 11 decreases, the temperature of the thermocouple exposed from the primary cooling water rises. Therefore, each thermocouple measures a different cooling water temperature, and a temperature difference is generated. Determines that the water in the reactor vessel 11 has decreased. In addition, although the heating type thermocouple type was applied and demonstrated as the water level meter 41, it is not limited to this system.

収納管42は、所定長さを有した円筒形状をなし、長手方向に沿って形成された支持孔内に水位計41が収納されている。なお、図1では、収納管42内に1本の水位計41(熱電対)だけを収納したものを図示しているが、実際には、複数の水位計が収納される。収納管42は、大径の本体部51は、本体部51より小径の上小径部52と、本体部51より小径の下小径部53とから構成され、本体部51と上小径部52との間に上段付き部54が形成され、本体部51と下小径部53との間に下段付き部55が形成されている。この上段付き部54と下段付き部55は、リング形状をなしているが、リング形状に限定されるものではない。   The storage tube 42 has a cylindrical shape having a predetermined length, and the water level gauge 41 is stored in a support hole formed along the longitudinal direction. Although FIG. 1 shows a case in which only one water level meter 41 (thermocouple) is stored in the storage tube 42, a plurality of water level meters are actually stored. The storage tube 42 includes a large-diameter main body 51 having an upper small diameter portion 52 having a smaller diameter than the main body portion 51 and a lower small diameter portion 53 having a smaller diameter than the main body portion 51. An upper stepped portion 54 is formed therebetween, and a lower stepped portion 55 is formed between the main body portion 51 and the lower small diameter portion 53. The upper stepped portion 54 and the lower stepped portion 55 have a ring shape, but are not limited to the ring shape.

炉内構造物側の支持部材としての上部炉心板20は、上面部に支持管(支持部材)61が固定されている。支持管61は、軸方向に沿って同径である円筒形状をなし、内径が収納管42の本体部51の外径より大きく設定されている。一方、原子炉容器蓋13は、軸方向に貫通する取付孔13aに管台62が貫通して固定されている。管台62は、円筒形状をなす本体62aと、本体62aの上部に形成されたリング形状をなすフランジ部62bと、フランジ部62bの中心に形成された貫通孔62cと、本体62aの下部に形成された傘形状をなす拡径部62dとから構成されている。   A support tube (support member) 61 is fixed to an upper surface portion of the upper core plate 20 as a support member on the in-furnace structure side. The support tube 61 has a cylindrical shape having the same diameter along the axial direction, and the inner diameter is set larger than the outer diameter of the main body 51 of the storage tube 42. On the other hand, the reactor vessel lid 13 is fixed with a nozzle 62 passing through an attachment hole 13a penetrating in the axial direction. The nozzle 62 is formed in a cylindrical main body 62a, a ring-shaped flange 62b formed in the upper part of the main body 62a, a through hole 62c formed in the center of the flange 62b, and a lower part of the main body 62a. And an enlarged-diameter portion 62d having an umbrella shape.

そして、収納管42は、下部が上部炉心板20に固定された支持管61に支持される一方、上部が原子炉容器蓋13に固定された管台62に対して着脱自在に支持される。   The storage tube 42 is supported by a support tube 61 whose lower portion is fixed to the upper core plate 20, while the upper portion is detachably supported with respect to a nozzle 62 fixed to the reactor vessel lid 13.

即ち、収納管42は、本体部51の下端部が支持管61内に配置され、収納管42と支持管61との間にリーフスプリング(位置決め部材)63が介装されることで、位置決め保持される。リーフスプリング63は、円筒形状をなし、上部のフランジ63aが支持管61の上端に配置され、フランジ63aから垂下した複数の支持片63bが支持管61内に侵入し、収納管42の外周面に押圧している。そのため、収納管42は、リーフスプリング63の各支持片63bにより中心側に押圧されることで、上部炉心板20に対して支持管61の中心位置で直立した状態で維持され、且つ、軸方向(長手方向)に沿って移動自在に支持される。   That is, the storage tube 42 is positioned and held by the lower end portion of the main body 51 being disposed in the support tube 61 and a leaf spring (positioning member) 63 interposed between the storage tube 42 and the support tube 61. Is done. The leaf spring 63 has a cylindrical shape, the upper flange 63a is disposed at the upper end of the support pipe 61, and a plurality of support pieces 63b suspended from the flange 63a penetrates into the support pipe 61, and enters the outer peripheral surface of the storage pipe 42. Pressing. Therefore, the storage tube 42 is maintained in an upright state at the center position of the support tube 61 with respect to the upper core plate 20 by being pressed toward the center by the support pieces 63b of the leaf spring 63, and is axially It is supported movably along (longitudinal direction).

また、収納管42は、下部と上部炉心板20との間に圧縮コイルばね(付勢部材)64が介装されている。圧縮コイルばね64は、一端部が上部炉心板20の上面に押圧し、他端部が収納管42の下段付き部55に押圧している。そのため、収納管42は、圧縮コイルばね64の付勢力により鉛直方向の上方側に付勢支持される。   The storage tube 42 has a compression coil spring (biasing member) 64 interposed between the lower part and the upper core plate 20. One end of the compression coil spring 64 is pressed against the upper surface of the upper core plate 20, and the other end is pressed against the lower stepped portion 55 of the storage tube 42. Therefore, the storage tube 42 is urged and supported on the upper side in the vertical direction by the urging force of the compression coil spring 64.

一方、収納管42は、上部が管台62内に配置され、上小径部52が貫通孔62cに貫通している。そして、収納管42は、上段付き部54と管台62のフランジ部62bとの間にリング形状をなすシール部材65が介装され、このシール部材65が押し潰された状態で、上小径部52がクリップ(係止部材)66により管台62のフランジ部62bに着脱自在に係止されている。   On the other hand, the upper portion of the storage tube 42 is disposed in the nozzle 62, and the upper small diameter portion 52 penetrates the through hole 62c. The storage tube 42 has a ring-shaped seal member 65 interposed between the upper stepped portion 54 and the flange portion 62b of the nozzle 62, and the upper small-diameter portion in a state where the seal member 65 is crushed. 52 is detachably locked to the flange portion 62 b of the nozzle 62 by a clip (locking member) 66.

収納管42は、上小径部52が管台62に係止されたとき、下小径部53が上部炉心板20から離間し、両者の間に隙間が確保されている。このとき、収納管42は、圧縮コイルばね64の付勢力によりシール部材65が押圧される方向に付勢支持される。   In the storage tube 42, when the upper small diameter portion 52 is locked to the nozzle 62, the lower small diameter portion 53 is separated from the upper core plate 20, and a gap is secured between them. At this time, the storage tube 42 is biased and supported in the direction in which the seal member 65 is pressed by the biasing force of the compression coil spring 64.

ここで、本実施形態の原子炉水位検出装置の作用について説明する。   Here, the operation of the reactor water level detection device of the present embodiment will be described.

原子炉容器11に水位検出装置40を装着するとき、原子炉容器本体12から原子炉容器蓋13が取り外された状態で、まず、上部炉心板20に固定された支持管61にリーフスプリング63及び圧縮コイルばね64を装着し、水位計41が収納された収納管42を支持管61内に挿入する。ここで、収納管42は、下部が圧縮コイルばね64に弾性支持され、外周面がリーフスプリング63により支持管61に支持されることで径方向の位置決めがなされる。次に、収納管42の上段付き部54にシール部材65を装着し、クレーンを用いて管台62が固定された原子炉容器蓋13を下降し、収納管42の上小径部52を管台62の貫通孔62cに貫通させ、原子炉容器本体12上に載置する。   When the water level detector 40 is attached to the reactor vessel 11, first, with the reactor vessel lid 13 removed from the reactor vessel body 12, first, a leaf spring 63 and a leaf spring 63 are attached to the support tube 61 fixed to the upper core plate 20. A compression coil spring 64 is attached, and the storage tube 42 in which the water level gauge 41 is stored is inserted into the support tube 61. Here, the lower portion of the storage tube 42 is elastically supported by the compression coil spring 64, and the outer peripheral surface is supported by the support tube 61 by the leaf spring 63, thereby positioning in the radial direction. Next, a seal member 65 is attached to the upper stepped portion 54 of the storage tube 42, the reactor vessel lid 13 to which the nozzle 62 is fixed is lowered using a crane, and the upper small diameter portion 52 of the storage tube 42 is moved to the nozzle. The through holes 62 c of the 62 are passed through and placed on the reactor vessel main body 12.

このとき、収納管42は、自重により圧縮コイルばね64を圧縮した下降位置にあることから、図示しない治具を用いて上小径部52を用いて収納管42を上昇させることで、上段付き部54と管台62のフランジ部62bとの間にあるシール部材65を押し潰す。そして、収納管42の上昇位置で、シール部材65が押し潰された状態で、上小径部52にクリップ66を係止することで、収納管42が管台62に連結される。そして、ナット15(図2参照)を締結して原子炉容器本体12に原子炉容器蓋13を固定する。   At this time, since the storage tube 42 is in a lowered position where the compression coil spring 64 is compressed by its own weight, the upper tube portion 42 is raised by using the upper small diameter portion 52 by using a jig (not shown). The seal member 65 located between 54 and the flange 62b of the nozzle 62 is crushed. The storage tube 42 is connected to the nozzle 62 by engaging the clip 66 with the upper small-diameter portion 52 with the seal member 65 being crushed at the raised position of the storage tube 42. Then, the nut 15 (see FIG. 2) is fastened to fix the reactor vessel lid 13 to the reactor vessel body 12.

一方、炉内構造物のメンテナンス作業を実施するとき、まず、ナット15(図2参照)を弛緩して原子炉容器本体12と原子炉容器蓋13の締結を解除すると共に、収納管42の上小径部52に係止したクリップ66を取り外し、原子炉容器蓋13の管台62と収納管42との連結を解除する。このとき、収納管42は、管台62に対する上小径部52の係止が解除されることで下降するが、下部が圧縮コイルばね64に支持されることで、上部炉心板20への衝突が防止される。   On the other hand, when performing maintenance work on the reactor internal structure, first, the nut 15 (see FIG. 2) is loosened to release the fastening of the reactor vessel body 12 and the reactor vessel lid 13 and The clip 66 locked to the small diameter portion 52 is removed, and the connection between the nozzle 62 of the reactor vessel lid 13 and the storage tube 42 is released. At this time, the storage tube 42 is lowered by releasing the locking of the upper small diameter portion 52 with respect to the nozzle 62, but the lower portion is supported by the compression coil spring 64, so that the collision with the upper core plate 20 is prevented. Is prevented.

次に、クレーンを用いて管台62が固定された原子炉容器蓋13を上昇し、収納管42の上小径部52を管台62の貫通孔62cから抜き取る。このとき、収納管42は、下部が圧縮コイルばね64に弾性支持され、外周面がリーフスプリング63により支持管61に支持されることで、上部炉心板20に自立して支持される。この状態で、取り出しや燃料集合体の交換などの作業が実施される。   Next, the reactor vessel lid 13 to which the nozzle 62 is fixed is lifted using a crane, and the upper small diameter portion 52 of the storage pipe 42 is extracted from the through hole 62 c of the nozzle 62. At this time, the lower portion of the storage tube 42 is elastically supported by the compression coil spring 64 and the outer peripheral surface is supported by the support tube 61 by the leaf spring 63, so that the storage tube 42 is supported by the upper core plate 20 independently. In this state, operations such as removal and replacement of the fuel assembly are performed.

このように本実施形態の原子炉水位検出装置にあっては、一次冷却材の水位を検出する水位計41と、水位計41を収納する収納管42とを備え、収納管42は、下部が上部炉心板(支持部材)20に支持される一方、上部が原子炉容器蓋13に対して着脱自在に支持される。   As described above, the reactor water level detection device according to the present embodiment includes the water level meter 41 for detecting the water level of the primary coolant and the storage pipe 42 for storing the water level gauge 41. While supported by the upper core plate (support member) 20, the upper portion is detachably supported with respect to the reactor vessel lid 13.

従って、原子炉のメンテナンス時に、原子炉容器本体12から原子炉容器蓋13を取り外したとき、原子炉容器蓋13に対して収納管42が分離されて上部炉心板20側に安定して支持される。水位計41が挿入された収納部材42が、原子炉容器蓋から分離されることで、水位計を収納部材から引き抜く、或いは水位計を収納部材に挿入するといった作業は不要となる。そのため、原子炉のメンテナンスに係る作業時間が短縮されるとともに、作業者の被曝量も低減され、原子炉のメンテナンス作業の作業性の向上を図ることができる。   Therefore, when the reactor vessel lid 13 is removed from the reactor vessel body 12 during the maintenance of the reactor, the storage tube 42 is separated from the reactor vessel lid 13 and is stably supported on the upper core plate 20 side. The Since the storage member 42 into which the water level gauge 41 is inserted is separated from the reactor vessel lid, the operation of pulling out the water level gauge from the storage member or inserting the water level gauge into the storage member becomes unnecessary. For this reason, the work time related to the maintenance of the reactor is shortened, and the exposure amount of the worker is also reduced, so that the workability of the maintenance work of the reactor can be improved.

本実施形態の原子炉水位検出装置では、原子炉容器蓋13に管台62を固定し、収納管42の上端部が管台62を貫通し、クリップ66により着脱自在に係止されている。従って、クリップ66を操作するだけで、原子炉容器蓋13の管台62に対して収納管42が着脱自在となり、原子炉容器本体12に対して原子炉容器蓋13を昇降させるだけで、原子炉容器蓋13を収納管42から分離、または、原子炉容器蓋13を収納管42に装着することができる。   In the reactor water level detection device of this embodiment, the nozzle 62 is fixed to the reactor vessel lid 13, and the upper end portion of the storage pipe 42 penetrates the nozzle 62 and is detachably locked by a clip 66. Accordingly, the storage tube 42 can be freely attached to and detached from the nozzle 62 of the reactor vessel lid 13 simply by operating the clip 66, and the atomic vessel lid 13 can be moved up and down with respect to the reactor vessel body 12. The reactor vessel lid 13 can be separated from the storage tube 42 or the reactor vessel lid 13 can be attached to the storage tube 42.

本実施形態の原子炉水位検出装置では、収納管42に本体部51と上小径部52とを設け、本体部51と上小径部52との間に上段付き部54を設けられ、上段付き部54と管台62との間にシール部材65を介装している。従って、収納管42の上段付き部54と管台62とを互いに接近する方向に移動するだけで、シール部材65を収納管42と管台62に密着させ、この密着状態でクリップ66により収納管42を係止すればよく、シール性及びシール装着性を向上することができる。   In the reactor water level detection device of the present embodiment, the storage pipe 42 is provided with a main body 51 and an upper small diameter portion 52, an upper stepped portion 54 is provided between the main body 51 and the upper small diameter portion 52, and an upper stepped portion is provided. A seal member 65 is interposed between the nozzle 54 and the nozzle 62. Therefore, the seal member 65 is brought into close contact with the storage tube 42 and the nozzle 62 only by moving the upper stepped portion 54 of the storage tube 42 and the nozzle 62 in a direction approaching each other. What is necessary is just to latch 42 and can improve sealing performance and seal mounting | wearing property.

本実施形態の原子炉水位検出装置では、上部炉心板20に支持管61を固定し、収納管42の下端部を支持管61により長手方向に沿って移動自在に支持すると共に、圧縮コイルばね64によりシール部材65が押圧される方向に付勢支持している。従って、管台62に対して収納管42を上方に移動させることで、シール部材65を収納管42と管台62に密着させることができ、この密着状態でクリップ66により収納管42を係止すればよい。また、クリップ66を取り外して収納管42の係止状態を解除すると、収納管42が自重により下降するが、収納管42は圧縮コイルばね64の付勢力により支持されることから、上部炉心板20への衝突が防止され、収納管42の損傷を防止することができる。   In the reactor water level detection device of the present embodiment, the support tube 61 is fixed to the upper core plate 20, and the lower end portion of the storage tube 42 is supported by the support tube 61 so as to be movable along the longitudinal direction. Therefore, the seal member 65 is biased and supported in the direction in which the seal member 65 is pressed. Accordingly, by moving the storage tube 42 upward with respect to the nozzle 62, the seal member 65 can be brought into close contact with the storage tube 42 and the nozzle 62, and the storage tube 42 is locked by the clip 66 in this tight contact state. do it. Further, when the clip 66 is removed to release the locked state of the storage tube 42, the storage tube 42 is lowered by its own weight. However, since the storage tube 42 is supported by the urging force of the compression coil spring 64, the upper core plate 20. Can be prevented and damage to the storage tube 42 can be prevented.

本実施形態の原子炉水位検出装置では、収納管42を圧縮コイルばね64の付勢力により下端部を上部炉心板20から離間して支持している。従って、管台62に対して収納管42の移動量を確保してシール部材65の装着性を向上することができると共に、収納管42の下降時の衝撃を圧縮コイルばね64により緩和して収納管42の損傷を防止することができる。   In the reactor water level detection device of the present embodiment, the storage tube 42 is supported by the urging force of the compression coil spring 64 so that the lower end portion is separated from the upper core plate 20. Accordingly, the amount of movement of the storage tube 42 relative to the nozzle 62 can be secured to improve the mounting performance of the seal member 65, and the impact when the storage tube 42 is lowered is relaxed by the compression coil spring 64 and stored. Damage to the tube 42 can be prevented.

本実施形態の原子炉水位検出装置では、支持管61を筒形状とし、収納管42の下端部を支持管61内に配置し、支持管61と収納管42との間に収納管42を位置決め保持するリーフスプリング63を設けている。従って、収納管42は、リーフスプリング63を介して支持管61に支持されることから、収納管42が上部炉心板20に対して所定の位置に安定して支持されることとなり、原子炉容器蓋13を容易に原子炉容器本体12に取付けることができる。   In the reactor water level detection device of the present embodiment, the support tube 61 has a cylindrical shape, the lower end portion of the storage tube 42 is disposed in the support tube 61, and the storage tube 42 is positioned between the support tube 61 and the storage tube 42. A holding leaf spring 63 is provided. Accordingly, since the storage tube 42 is supported by the support tube 61 via the leaf spring 63, the storage tube 42 is stably supported at a predetermined position with respect to the upper core plate 20, and the reactor vessel The lid 13 can be easily attached to the reactor vessel main body 12.

また、本実施形態の原子炉にあっては、原子炉水位検出装置40を原子炉容器11内に設けている。従って、原子炉容器11内の一次冷却水の水位を高精度に検出することができると共に、原子炉のメンテナンス作業の作業性の向上を図ることができる。   Further, in the nuclear reactor of the present embodiment, the reactor water level detection device 40 is provided in the reactor vessel 11. Therefore, the water level of the primary cooling water in the reactor vessel 11 can be detected with high accuracy, and the workability of the maintenance work of the reactor can be improved.

なお、上述した実施形態にて、付勢部材としての圧縮コイルばね64を収納部材としての収納管42の下方に配置したが、この位置に限定されるものではない。例えば、収納部材における長手方向の中間部にフランジ部や段付き部を設ける一方、支持部材にばね受け部を設け、付勢部材をフランジ部や段付き部とばね受け部との間に介装してもよい。また、収納部材を2分割とし、付勢部材を上部収納部材と下部収納部材との間に介装してもよい。更に、付勢部材は、圧縮コイルばね64に限らず、引っ張りばね、ゴム部材、樹脂部材などにより構成してもよい。   In the above-described embodiment, the compression coil spring 64 as the urging member is disposed below the storage tube 42 as the storage member. However, the present invention is not limited to this position. For example, a flange portion or a stepped portion is provided in the intermediate portion in the longitudinal direction of the storage member, while a support member is provided with a spring receiving portion, and the biasing member is interposed between the flange portion or the stepped portion and the spring receiving portion. May be. Further, the storage member may be divided into two, and the urging member may be interposed between the upper storage member and the lower storage member. Further, the urging member is not limited to the compression coil spring 64 but may be constituted by a tension spring, a rubber member, a resin member, or the like.

また、上述した実施形態にて、水位検出装置40を炉内構造物側の支持部材としての上部炉心板20上に支持したが、上部炉心支持板19など、他の炉内構造物側の支持部材に支持するように構成してもよい。   Further, in the embodiment described above, the water level detection device 40 is supported on the upper core plate 20 as the support member on the reactor internal structure side. However, the support on the other reactor internal structure side such as the upper core support plate 19 is supported. You may comprise so that it may support in a member.

また、上述した実施形態にて、原子炉を加圧水型原子炉として説明したが、沸騰水型原子炉(BWR:Boiling Water Reactor)や高速増殖炉(FBR:Fast Breeder Reactor)に適用してもよい。   Moreover, although the nuclear reactor was demonstrated as a pressurized water reactor in embodiment mentioned above, you may apply to a boiling water reactor (BWR: Boiling Water Reactor) and a fast breeder reactor (FBR: Fast Breeder Reactor). .

10 加圧水型原子炉
11 原子炉容器
12 原子炉容器本体
13 原子炉容器蓋
18 炉心槽
19 上部炉心支持板
20 上部炉心板(支持部材)
25 炉心
26 燃料集合体
27 制御棒
40 水位検出装置
41 水位計
42 収納管(収納部材)
51 本体部
52 上小径部
53 下小径部
54 上段付き部
55 下段付き部
61 支持管(支持部材)
62 管台
63 リーフスプリング(位置決め部材)
64 圧縮コイルばね(付勢部材)
65 シール部材
66 クリップ(係止部材)
DESCRIPTION OF SYMBOLS 10 Pressurized water reactor 11 Reactor vessel 12 Reactor vessel body 13 Reactor vessel lid 18 Core tank 19 Upper core support plate 20 Upper core plate (support member)
25 Core 26 Fuel assembly 27 Control rod 40 Water level detection device 41 Water level gauge 42 Storage pipe (storage member)
51 Main body portion 52 Upper small diameter portion 53 Lower small diameter portion 54 Upper stepped portion 55 Lower stepped portion 61 Support pipe (support member)
62 Tubular base 63 Leaf spring (positioning member)
64 Compression coil spring (biasing member)
65 Seal member 66 Clip (locking member)

Claims (7)

冷却材の水位を検出する水位計と、
前記水位計を収納する収納部材と、
を備え、
前記収納部材は、下部が炉内構造物側に設けられる支持部材に支持される一方、上部が原子炉容器蓋に対して着脱自在に支持される、
ことを特徴とする原子炉水位検出装置。
A water level gauge that detects the coolant level,
A storage member for storing the water level gauge;
With
The storage member is supported by a support member whose lower part is provided on the reactor internal structure side, while its upper part is detachably supported with respect to the reactor vessel lid.
A reactor water level detection device characterized by that.
前記原子炉容器蓋に管台が固定され、前記収納部材は、上端部が前記管台を貫通し、係止部材により着脱自在に係止されることを特徴とする請求項1に記載の原子炉水位検出装置。   2. The atom according to claim 1, wherein a nozzle is fixed to the reactor vessel lid, and an upper end portion of the storage member penetrates the nozzle and is detachably locked by a locking member. Reactor water level detection device. 前記収納部材は、本体部と上小径部とが設けられ、前記本体部と前記上小径部との間に段付き部が設けられ、前記段付き部と前記管台との間にシール部材が介装されることを特徴とする請求項2に記載の原子炉水位検出装置。   The storage member is provided with a main body portion and an upper small diameter portion, a stepped portion is provided between the main body portion and the upper small diameter portion, and a seal member is provided between the stepped portion and the nozzle. The reactor water level detection device according to claim 2, wherein the reactor water level detection device is interposed. 前記炉内構造物に支持部材が固定され、前記収納部材は、下端部が前記支持部材により長手方向に沿って移動自在に支持されると共に、付勢部材により前記シール部材が押圧される方向に付勢支持されることを特徴とする請求項3に記載の原子炉水位検出装置。   A support member is fixed to the in-furnace structure, and the lower end portion of the storage member is supported by the support member so as to be movable along the longitudinal direction, and the seal member is pressed by the biasing member. The reactor water level detection device according to claim 3, wherein the reactor water level detection device is biased and supported. 前記収納部材は、前記付勢部材の付勢力により下端部が前記炉内構造物から離間して支持されることを特徴とする請求項4に記載の原子炉水位検出装置。   The reactor water level detection device according to claim 4, wherein a lower end portion of the storage member is supported by the urging force of the urging member so as to be separated from the reactor internal structure. 前記支持部材は、筒形状をなし、前記収納部材は、下端部が前記支持部材内に配置され、前記支持部材と前記収納部材との間に前記収納部材を位置決め保持する位置決め部材が設けられることを特徴とする請求項4または請求項5に記載の原子炉水位検出装置。   The support member has a cylindrical shape, the storage member has a lower end portion disposed in the support member, and a positioning member that positions and holds the storage member is provided between the support member and the storage member. The reactor water level detection apparatus according to claim 4 or 5, characterized in that: 請求項1から請求項6のいずれか一項に記載の原子炉水位検出装置が設けられることを特徴とする
原子炉。
A nuclear reactor comprising the reactor water level detection device according to any one of claims 1 to 6.
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JPS6473297A (en) * 1987-09-16 1989-03-17 Toshiba Corp Reactor instrumentation pipe
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JPH02271298A (en) * 1989-01-25 1990-11-06 Framatome Et Cogema <Fragema> Sealing device for instrument pillar penetrating top of pressurized water reactor
JPH04332897A (en) * 1990-12-10 1992-11-19 General Electric Co <Ge> Monitor for level in container of voilling water type nuclear reactor
JPH0862378A (en) * 1994-08-18 1996-03-08 Mitsubishi Heavy Ind Ltd Aligning holding structure for sensor housing pipe
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Patent Citations (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5847217A (en) * 1981-09-01 1983-03-18 コンバツシヨン・エンヂニアリング・インコ−ポレ−テツド Junction thermocouple liquid-level measuring device
JPS6473297A (en) * 1987-09-16 1989-03-17 Toshiba Corp Reactor instrumentation pipe
JPH02168196A (en) * 1988-08-25 1990-06-28 Framatome Et Cogema <Fragema> Measuring apparatus for core of pressurized
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JPH02271298A (en) * 1989-01-25 1990-11-06 Framatome Et Cogema <Fragema> Sealing device for instrument pillar penetrating top of pressurized water reactor
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