JP3153833B2 - Guide device for neutron flux detector in reactor - Google Patents

Guide device for neutron flux detector in reactor

Info

Publication number
JP3153833B2
JP3153833B2 JP30943992A JP30943992A JP3153833B2 JP 3153833 B2 JP3153833 B2 JP 3153833B2 JP 30943992 A JP30943992 A JP 30943992A JP 30943992 A JP30943992 A JP 30943992A JP 3153833 B2 JP3153833 B2 JP 3153833B2
Authority
JP
Japan
Prior art keywords
reactor
instrumentation
core
neutron flux
detector
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired - Lifetime
Application number
JP30943992A
Other languages
Japanese (ja)
Other versions
JPH06138283A (en
Inventor
川 利 郎 市
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Mitsubishi Heavy Industries Ltd
Original Assignee
Mitsubishi Heavy Industries Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Mitsubishi Heavy Industries Ltd filed Critical Mitsubishi Heavy Industries Ltd
Priority to JP30943992A priority Critical patent/JP3153833B2/en
Publication of JPH06138283A publication Critical patent/JPH06138283A/en
Application granted granted Critical
Publication of JP3153833B2 publication Critical patent/JP3153833B2/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

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Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Description

【発明の詳細な説明】DETAILED DESCRIPTION OF THE INVENTION

【0001】[0001]

【産業上の利用分野】本発明は、主として加圧水型軽水
炉などの原子炉の炉内核計装設備のうち炉内中性子束検
出器を筒体を通して燃料集合体内へ案内する炉内中性子
束検出器の案内装置に関するものである。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention mainly relates to a neutron flux detector in a reactor for guiding a neutron flux detector in a reactor through a cylinder into a fuel assembly in a nuclear instrumentation facility of a nuclear reactor such as a pressurized water reactor. The present invention relates to a guide device.

【0002】[0002]

【従来の技術】図5に従来の核計装設備及び核計装案内
構造を示す。図5に示す核計装設備は、原子炉容器Aの
下部貫通部としての計装用管台14を通じて炉心下部か
ら核計装検出器5を挿入する方式で、検出器5と炉内計
装用シンブル7との間に微小間隙を有する同一内径の筒
体で案内する構造である。このため検出器5の案内経路
となる炉内計装用シンブル7は、図5に示すように、大
きな曲げ半径が必要であり、原子炉容器外部に曲がり部
を設けている。
2. Description of the Related Art FIG. 5 shows a conventional nuclear instrumentation facility and a nuclear instrumentation guide structure. The nuclear instrumentation equipment shown in FIG. 5 is a system in which the nuclear instrumentation detector 5 is inserted from the lower part of the core through the instrumentation nozzle 14 as a lower penetration part of the reactor vessel A, and the detector 5 and the in-core instrumentation thimble 7 It is a structure of guiding by a cylindrical body having the same inner diameter with a minute gap between them. For this reason, the in-core instrumentation thimble 7 serving as a guide path for the detector 5 needs a large bending radius as shown in FIG. 5, and has a bent portion outside the reactor vessel.

【0003】また、炉内計装用シンブル7は、燃料交換
時に、燃料集合体から引き抜く必要があり、シールテー
ブル28部に設けられたスエージロックシールを開放し
て引き抜く。このシールテーブル28の上部には、隔離
弁29を設けている。上記検出器5は信号引き出し用の
同軸ケーブルに結合されており、炉内への挿入または引
き抜きは、駆動装置13で行い、また、検出器の挿入位
置の選択は、検出器通路選択機23,24で行う。
[0003] The in-furnace instrumentation thimble 7 needs to be pulled out of the fuel assembly at the time of refueling, and the swage lock seal provided on the seal table 28 is opened and pulled out. An isolation valve 29 is provided above the seal table 28. The detector 5 is connected to a coaxial cable for extracting a signal. Insertion or extraction of the detector into or from the furnace is performed by a driving device 13, and the insertion position of the detector is selected by a detector path selector 23, Perform at 24.

【0004】[0004]

【発明が解決しようとする課題】従来の原子炉の核計装
設備では、検出器5の回りに微小間隙を有する同一内径
の筒体内部に検出挿入及び引き抜きするため大きな曲げ
半径が必要であり、原子炉容器Aの外部に曲がり部を設
け、炉心より下部に設置された原子炉容器Aの下部の計
装用管台14を通じて検出器を挿入している。
In the conventional nuclear instrumentation equipment of a nuclear reactor, a large bending radius is required for detecting and inserting into and extracting from the inside of a cylinder having the same inside diameter having a minute gap around the detector 5, A bent portion is provided outside the reactor vessel A, and the detector is inserted through an instrumentation nozzle 14 below the reactor vessel A installed below the core.

【0005】従って、原子炉容器Aの下部に計装用管台
14や炉内計装引出管(コンジットチューブ)がある
と、配置上、原子炉容器Aの下側に大きな空間を必要と
する。また施工不良または経年劣化等による炉心下部か
ら冷却材が漏洩する潜在性がある。
Therefore, if the instrumentation nozzle 14 and the in-core instrumentation outlet pipe (conduit tube) are provided below the reactor vessel A, a large space is required below the reactor vessel A due to the arrangement. In addition, there is a possibility that coolant may leak from the lower part of the core due to poor construction or aging.

【0006】一方、これらの点を解決していくために原
子炉容器A下部の計装用管台14を廃止し、核計装用の
検出器5を炉心の上部から挿入する方式の採用が考えら
れる。しかし、原子炉容器Aの蓋上部には制御棒駆動装
置があり、従来の方式を原子炉容器Aの蓋上部に適用す
ることは困難である。
On the other hand, in order to solve these problems, it is conceivable to adopt a system in which the instrumentation nozzle 14 at the lower part of the reactor vessel A is abolished and the detector 5 for nuclear instrumentation is inserted from above the core. However, there is a control rod drive device on the upper part of the reactor vessel A, and it is difficult to apply the conventional method to the upper part of the reactor vessel A.

【0007】このような事情から、この発明は核計装用
検出器を炉心の上部から挿入する方式が可能となる検出
器の案内支持構造を具備すると共に、燃料交換時の検出
器の案内支持構造の取扱作業性を向上できる炉内中性子
束検出器の案内装置を得ることを目的とする。
[0007] Under such circumstances, the present invention is provided with a guide support structure for a detector capable of inserting a detector for nuclear instrumentation from above the reactor core, and a guide support structure for the detector at the time of refueling. It is an object of the present invention to obtain a guide device for a neutron flux detector in a furnace that can improve handling efficiency.

【0008】[0008]

【課題を解決するための手段】この発明に係る炉内中性
子束検出器の案内装置は、原子炉内の燃料集合体内へ炉
内中性子束検出器をガイドする下部の筒体が挿通された
案内管と、該案内管を支持する上部炉心支持柱を支持す
る上部炉心支持板と、原子炉内の一括吊り上げ板上に設
立されて、原子炉容器蓋を貫通する計装用管台と、該計
装用管台内の炉内計装支持柱内に設置された上部の筒体
と、該上部の筒体と上記下部の筒体との間に上部の筒体
及び下部の筒体より径を大きくした中間部の筒体が接続
され、該中間部の筒体を小曲率でガイド支持する支持部
とを備えていることを特徴とする。
According to the present invention, there is provided a guide device for a neutron flux detector in a reactor, wherein a lower cylinder for guiding the neutron flux detector in the reactor is inserted into a fuel assembly in a reactor. A pipe, an upper core support plate for supporting an upper core support column for supporting the guide tube, an instrumentation nozzle installed on a batch lifting plate in the reactor, and penetrating a reactor vessel lid; An upper cylindrical body installed in a furnace instrumentation support column in a mounting nozzle, and an upper cylindrical body between the upper cylindrical body and the lower cylindrical body
And the middle cylinder with a larger diameter than the lower cylinder is connected
And a support member for guiding and supporting the intermediate body at a small curvature .

【0009】また、この発明に係る他の炉内中性子束検
出器の案内装置は、一括吊り上げ板の上記原子炉容器蓋
による保持を開蓋により解除可能にして、該一括吊り上
げ板を上記各筒体とともに吊り上げ可能にしたものであ
る。
Further, another guiding device for a neutron flux detector in a reactor according to the present invention is such that the holding of the batch lifting plate by the reactor vessel lid can be released by opening the lid, and the batch lifting plate is connected to each of the cylinders. It can be lifted with the body.

【0010】[0010]

【作用】この発明における下部、上部および中間部の筒
体は、原子炉容器内に配置され、かつ一部が原子炉容器
蓋を貫通するように連結され、中間部の筒体には曲率の
小さい曲がり部を設けることで、炉内中性子束検出器の
案内を容易化するとともに、炉内計装設備としてコンパ
クト配置を可能にし、設備コストの低減を図れるように
する。
According to the present invention, the lower, upper and intermediate cylinders are disposed in the reactor vessel and partially connected to penetrate the reactor vessel lid, and the intermediate cylinder has a curvature. By providing a small bent portion, the guide of the neutron flux detector in the furnace is facilitated, and a compact arrangement as the in-core instrumentation equipment is enabled, so that the equipment cost can be reduced.

【0011】また、各筒体は吊り上げ板上の計装用管台
や支持部材などに支持される構成となっているため、そ
の一括吊り上げ板を、原子炉容器蓋を開放した後、昇降
機を用いて吊り上げることで、各筒体とともに炉内中性
子束検出器を一括して引き上げられるようにし、これに
より燃料交換を容易化、迅速化する。
[0011] Further, since each cylindrical body is configured to be supported by an instrumentation nozzle, a support member, and the like on the lifting plate, the batch lifting plate is opened by opening the reactor vessel lid, and then using an elevator. By lifting, the neutron flux detector in the furnace together with each cylinder can be lifted at a time, thereby facilitating and speeding up refueling.

【0012】[0012]

【実施例】実施例1 以下、本発明の一実施例を図について説明する。図1は
本発明の炉内中性子束検出器を案内支持する構造を採用
した原子炉構造の概略図であり、図2はその炉内中性子
束検出器の案内構造を示す概略図である。まず、炉内中
性子束検出器を案内する筒体1a〜1c及びこれを支
持する炉内計装支持柱3、支持板4は原子炉容器15の
内部に設置された炉内中性子束検出器支持構造物の一括
吊り上げ板43の上面で支持される。
Embodiment 1 An embodiment of the present invention will be described below with reference to the drawings. FIG. 1 is a schematic view of a reactor structure employing a structure for guiding and supporting a neutron flux detector in a reactor of the present invention, and FIG. 2 is a schematic view showing a guide structure of the neutron flux detector in the reactor. First, the cylindrical bodies 1a to 1c for guiding the in-core neutron flux detector 5 , the in-core instrumentation support columns 3 and the support plate 4 for supporting the same are provided in the in-core neutron flux detector installed in the reactor vessel 15. It is supported on the upper surface of the batch lifting plate 43 of the support structure.

【0013】筒体1aの上部は筒体1aを支持する炉内
計装支持柱3の内部を通り、支持柱3上端のコノシール
10を貫通して、図1に示すように原子炉容器15の上
部に導かれる。原子炉容器15の蓋16の貫通部は、従
来から加圧水型軽水炉で用いられている炉内計装管台と
同型の管台8を使用する。
The upper portion of the cylindrical body 1a passes through the inside of the in-core instrumentation support column 3 for supporting the cylindrical body 1a, penetrates a cono seal 10 at the upper end of the support column 3, and as shown in FIG. Guided to the top. The penetrating portion of the lid 16 of the reactor vessel 15 uses a nozzle 8 of the same type as the in-core instrumentation nozzle conventionally used in a pressurized water light water reactor.

【0014】また、筒体1bは、管台部から炉内核計装
位置に導くため水平及び鉛直面内で曲がり部を持つ。筒
体1cの下部は、上部炉心支持柱18の内部に設置され
た案内管6及び燃料集合体20の炉内計装用シンブル7
に差し込まれ、炉内中性子束検出器5Aを炉心内部に導
く案内経路を形成している。
Further, the cylindrical body 1b has a bent portion in a horizontal and vertical plane for guiding from the nozzle section to the in-core nuclear instrumentation position. The lower portion of the cylindrical body 1c includes a guide tube 6 installed inside the upper core support column 18 and a thimble 7 for instrumentation of the fuel assembly 20 in the furnace.
To form a guide path for guiding the in-core neutron flux detector 5A into the core.

【0015】また、上記炉内中性子束検出器を案内す
る直線部及び曲がり部を持つ筒体1a〜1c及びこれを
支持する構造の詳細は、図2に示す通りであり、筒体1
aは従来から加圧水型軽水炉で用いられている炉内該計
装用シンブルと同様に可動式の炉内中性子束検出器
の間に微小の間隙を有し、図2に示す計装用管台8にお
けるコノシール10の貫通口径を小さくする。
Further, details of the cylinders 1a to 1c having the straight portion and the bent portion for guiding the in-core neutron flux detector 5 and the structure for supporting the same are as shown in FIG.
a has a minute gap between the movable in-core neutron flux detector 5 like the in-core instrument thimble conventionally used in pressurized water light water reactors, and the instrumentation nozzle shown in FIG. 8, the diameter of the through hole of the cono seal 10 is reduced.

【0016】図1において、この細径の筒体1aはこれ
を支持する炉内計装支持柱3の内部を通り、コノシール
10を貫通して原子炉の上部に導かれ、上端はスエージ
ロックシール11で冷却材の漏洩を遮断する。原子炉容
器蓋16の貫通部は従来から加圧水型軽水炉で用いられ
ている計装用管台8を使用する。この計装用管台8はマ
ーマンクランプ9の開閉により分解可能であり、燃料交
換時に、原子炉容器蓋16を吊り上げる前に開放する。
In FIG. 1, the small-diameter cylindrical body 1a passes through the inside of the in-core instrumentation support column 3 for supporting the cylindrical body 1a, passes through the cono-seal 10, and is guided to the upper part of the reactor. At 11, the leakage of the coolant is shut off. The penetrating portion of the reactor vessel lid 16 uses the instrumentation nozzle 8 conventionally used in a pressurized water reactor. The instrumentation nozzle 8 can be disassembled by opening and closing the Merman clamp 9, and is opened before lifting the reactor vessel lid 16 at the time of refueling.

【0017】筒体1bは図2に示すように、2箇所以上
の曲がり部と直線部を持つ筒体で、筒体1aの部分より
径が太い。筒体1bは、これを支持する支持柱4及び炉
内計装支持柱3から構成される一体型の構造物で支持さ
れる。この中間部の筒体1bは、上部の筒体1aより内
径が大きい筒体で構成されており、細径と太径の筒体の
接合部は溶接等により接合された継ぎ手2を有する構造
とし、別々に製作可能な構造とする。
As shown in FIG. 2, the cylinder 1b is a cylinder having two or more bent portions and straight portions, and has a diameter larger than that of the cylinder 1a. The cylindrical body 1b is supported by an integrated structure composed of a support column 4 for supporting the same and the in-furnace instrumentation support column 3. The cylinder 1b at the intermediate portion is constituted by a cylinder having an inner diameter larger than that of the upper cylinder 1a, and a joint between the small and large diameter cylinders has a joint 2 joined by welding or the like. And can be manufactured separately.

【0018】本発明の特徴は、このように曲がり部の内
径を大きくした筒体1bの案内経路を供することによ
り、原子炉容器16の頂部プレナムのように狭い領域内
において、案内管の曲げ半径が小さくても可動式の炉内
中性子束検出器を案内できることである。
A feature of the present invention is to provide a guide path for the cylindrical body 1b having a larger inner diameter of the bent portion, so that the bending radius of the guide tube can be reduced in a narrow area such as the top plenum of the reactor vessel 16. Is small enough to guide the movable neutron flux detector 5 in the reactor.

【0019】また、筒体1cは図2に示すように、上部
の筒体1aと同様に細径の筒体で構成され、下端は筒体
1aを挿入する時に、滑らかに挿入できるように角を落
とした砲弾型の端栓を接合した構造とする。原子炉の運
転時に筒体1cは、上部炉心支持柱18の案内管として
の炉内計装案内管6及び燃料集合体20の計装用シンブ
ル7内に挿入され、中性子束検出器を炉心内部に挿入
する経路を構成する。
As shown in FIG. 2, the cylindrical body 1c is formed of a small-diameter cylindrical body like the upper cylindrical body 1a, and the lower end has a square shape so that the cylindrical body 1a can be inserted smoothly. A structure in which shell-shaped end plugs from which are dropped are joined. During operation of the reactor, the cylinder 1c is inserted into the in-core instrumentation guide tube 6 as a guide tube for the upper core support column 18 and the instrumentation thimble 7 of the fuel assembly 20, and the neutron flux detector 5 is inserted into the core. Configure the path to be inserted into

【0020】従来型の燃料集合体は下部挿入式の炉内計
装に対応して、燃料集合体20の下部ノズル27を貫通
して計装用シンブル7内に挿入できる構造であるが、本
発明では、上部挿入式炉内計装を可能とするため、上部
ノズル26に貫通穴を開け、計装用シンブル7の上部か
ら筒体1cを挿入可能な構造とする。
The conventional fuel assembly has a structure which can be inserted into the instrumentation thimble 7 through the lower nozzle 27 of the fuel assembly 20 corresponding to the lower insertion type in-core instrumentation. Then, in order to enable the upper instrumentation type in-furnace instrumentation, a through hole is formed in the upper nozzle 26 so that the cylindrical body 1 c can be inserted from above the instrumentation thimble 7.

【0021】一方、燃料交換時は、上部炉心構造物を原
子炉容器15の外に吊り出す前に、上部炉心板19より
下側の燃料集合体20の計装用シンブル内に挿入された
筒体1cの下端が、上部炉心板19より上方に位置する
まで、図4に示す上部炉心構造物吊り上げ装置で吊り上
げ、このとき筒体1cが吊り上げ時に他の部材と接触し
て破損することの無いように取り扱う。
On the other hand, at the time of refueling, before the upper core structure is suspended from the reactor vessel 15, the cylindrical member inserted into the instrumentation thimble of the fuel assembly 20 below the upper core plate 19. Until the lower end of 1c is located above the upper core plate 19, it is lifted by the upper core structure lifting device shown in FIG. 4, so that the cylindrical body 1c does not come into contact with other members at the time of lifting and is damaged. Handle it.

【0022】図4は上部挿入方式の炉内計装設備の配置
例を示す。この例では、原子炉容器蓋16に取付けられ
た吊り上げ一体化構造物21の上部に設置したミサイル
シールド22上面に、検出器の通路選択機23,24を
配置し、駆動装置25を原子炉キャビティ内に設置する
ことにより、図5に示す従来型の炉内計装設備よりコン
パクトな配置を可能としている。
FIG. 4 shows an example of the arrangement of the instrumentation equipment in the furnace of the upper insertion type. In this example, on the upper surface of a missile shield 22 installed above a lifting integrated structure 21 attached to a reactor vessel lid 16, detector path selectors 23 and 24 are arranged, and a driving device 25 is connected to a reactor cavity. By installing the inside of the furnace, the arrangement can be more compact than the conventional in-core instrumentation equipment shown in FIG.

【0023】実施例2.本発明の炉内核計装検出器案内
構造物は原子炉容器15内に複数設置する必要があり、
個別に吊り上げ作業を行うと燃料交換作業時間が長くな
る。作業時間を短縮化するには、一度の吊り上げ作業で
全部の炉内核計装検出器案内構造物1を一括して吊り上
げる。
Embodiment 2 FIG. It is necessary to install a plurality of the nuclear instrumentation detector guide structures of the present invention in the reactor vessel 15,
Performing the lifting work individually increases the refueling work time. In order to shorten the working time, all the core instrumentation detector guide structures 1 in the furnace are lifted at one time by a single lifting work.

【0024】図4に示す一括吊り上げ構造は従来の上部
炉心構造物吊り上げ装置40に昇降機41を付け、原子
炉容器フランジ部に設置した一括吊り上げ板43で一度
に吊り上げる構造とする。炉内核計装支持柱下部固定部
12と一括吊り上げ板43の嵌め合い部は、炉内核計装
支持柱3が水平面及び鉛直面内で回転しないよう平面で
嵌合する構造とする。
The batch lifting structure shown in FIG. 4 has a structure in which an elevator 41 is attached to a conventional upper core structure lifting device 40 and is lifted at once by a batch lifting plate 43 installed on a flange portion of the reactor vessel. The fitting portion between the in-core core instrumentation support column lower fixed portion 12 and the collective lifting plate 43 has a structure in which the in-core core instrumentation support column 3 is fitted in a plane so as not to rotate in a horizontal plane and a vertical plane.

【0025】炉内核計装検出器案内構造の筒体1a〜1
cは、上部炉心構造物内部に吊り上げ時に、他の部材と
接触して破損することの無いように取り扱う。図4に示
す上部炉心構造物吊り上げ装置には、昇降機41を上死
点位置で固定するストッパー42を有する構造とする。
The cylindrical bodies 1a to 1 of the core instrumentation detector guide structure in the furnace
c is handled so as not to be damaged by contact with other members when lifted inside the upper core structure. The upper core structure lifting device shown in FIG. 4 has a structure having a stopper 42 for fixing the elevator 41 at the top dead center position.

【0026】炉内核計装支持柱3と一括吊り上げ板43
の吊り上げは、原子炉のクレーンを使用する。定期検査
時にポーラクレーンを使用せずに吊り上げ可能な構造と
するには、上部炉心構造物吊り上げ装置40に自動昇降
装置を設置し、吊り上げ機能を付加することで可能とな
る。
The core instrumentation support column 3 and the batch lifting plate 43
Is lifted using a crane of a nuclear reactor. In order to provide a structure that can be lifted without using a polar crane at the time of the periodic inspection, it is possible to install an automatic lifting device in the upper core structure lifting device 40 and add a lifting function.

【0027】[0027]

【発明の効果】以上のように、本発明によれば原子炉内
の燃料集合体内へ炉内中性子束検出器をガイドする下部
の筒体が挿通された案内管と、該案内管を支持する上部
炉心支持柱を支持する上部炉心支持板と、原子炉内の一
括吊り上げ板上に設立されて、原子炉容器蓋を貫通する
計装用管台と、該計装用管台内の炉内計装支持柱内に設
置された上部の筒体と、該上部の筒体と上記下部の筒体
との間に上部の筒体及び下部の筒体より径を大きくした
中間部の筒体が接続され、該中間部の筒体を支持部材に
より小曲率でガイド支持するように構成したので、既存
の原子炉で実績のある可動式炉内中性子束検出器を、従
来の案内構造に比べ小さな曲げ半径で案内でき、この構
造を適用すれば、原子炉頂部プレナムのように狭い領域
で、原子炉貫通位置から計装位置に検出器を案内し、炉
心上部より炉内核計装用検出器を挿入でき、これにより
原子炉容器下部の計装用管台や炉内計装引出管の引回し
が不要になり、原子炉容器下部の空間を必要としないの
で、コンパクトな配置ができる効果がある。
As described above, according to the present invention, the guide tube in which the lower cylinder for guiding the in-reactor neutron flux detector is inserted into the fuel assembly in the reactor, and the guide tube are supported. An upper core support plate that supports the upper core support column, an instrumentation nozzle that is established on the batch lifting plate in the reactor, and penetrates the reactor vessel lid, and an in-core instrumentation in the instrumentation nozzle. An upper cylinder installed in the support column, and a middle cylinder having a larger diameter than the upper cylinder and the lower cylinder between the upper cylinder and the lower cylinder. body are connected, the cylindrical body of the intermediate portion and then, is guide supporting at small curvature by a support member, a movable incore neutron flux detector proven in existing reactors, the conventional guide structure This structure can be guided with a smaller bend radius, and if this structure is applied, the reactor penetration in a narrow area like the reactor top plenum can be achieved. The detector can be guided from the position to the instrumentation position, and the detector for in-core nuclear instrumentation can be inserted from the upper part of the reactor core. Since there is no need for a space below the reactor vessel, there is an effect that compact arrangement is possible.

【0028】また、原子炉建屋基礎形状は、原子炉容器
下部を深く掘った形状としているが、原子炉容器下部の
空間を必要としない平坦な形状とすることができ、掘削
量の低減を図れる等、基礎工事においても有利となる。
更に、炉心より下部からの冷却材漏洩の潜在性を排除す
ることが可能になるという効果が得られる。
Further, the basic shape of the reactor building is such that the lower part of the reactor vessel is dug deep, but it can be made a flat shape which does not require the space under the reactor vessel, and the amount of excavation can be reduced. It is also advantageous for foundation work.
Further, there is an effect that it is possible to eliminate the possibility of coolant leakage from below the core.

【0029】また、この発明によれば一括吊り上げ板の
上記原子炉容器蓋による保持を開蓋により解除可能にし
て、該一括吊り上げ板を上記各筒体とともに吊り上げ可
能にしたので、燃料交換の作業の容易化並びに迅速化を
図れるという効果が得られる。
Further, according to the present invention, the holding of the batch lifting plate by the reactor vessel lid can be released by opening the lid, and the batch lifting plate can be lifted together with the respective cylinders. And speeding up can be achieved.

【図面の簡単な説明】[Brief description of the drawings]

【図1】本発明の一実施例による炉内中性子束検出器の
案内装置の要部を示す断面図である。
FIG. 1 is a cross-sectional view showing a main part of a guide device for a neutron flux detector in a reactor according to an embodiment of the present invention.

【図2】図1における案内装置を持った原子炉を示す断
面図である。
FIG. 2 is a sectional view showing a nuclear reactor having a guide device in FIG.

【図3】図1における炉内計装装置を示す配置図であ
る。
FIG. 3 is a layout view showing the in-furnace instrumentation device in FIG. 1;

【図4】図1における炉内計装装置の吊り上げ機能を示
す概略構成図である。
FIG. 4 is a schematic configuration diagram showing a lifting function of the in-furnace instrumentation device in FIG.

【図5】従来の炉内核計装設備を示す構成図である。FIG. 5 is a configuration diagram showing a conventional in-core nuclear instrumentation facility.

【符号の説明】[Explanation of symbols]

1a、1b、1c 筒体 4 支持板(支持部材) 炉内中性子束検出器 6 案内筒 8 計装用管台 16 原子炉容器蓋 17 上部炉心支持板 18 上部炉心支持柱 20 燃料集合体 43 一括吊り上げ板1a, 1b, 1c Cylindrical body 4 Support plate (support member) 5 In- core neutron flux detector 6 Guide cylinder 8 Instrumentation nozzle 16 Reactor vessel lid 17 Upper core support plate 18 Upper core support column 20 Fuel assembly 43 Batch Lifting plate

Claims (1)

(57)【特許請求の範囲】(57) [Claims] 【請求項1】 原子炉内の燃料集合体内へ炉内中性子束
検出器をガイドする下部の筒体が挿通された案内管と、
該案内管を支持する上部炉心支持柱を支持する上部炉心
支持板と、原子炉内の一括吊り上げ板上に設立されて、
原子炉容器蓋を貫通する計装用管台と、該計装用管台内
の炉内計装支持柱内に設置された上部の筒体と、該上部
の筒体と上記下部の筒体との間に上部の筒体及び下部の
筒体より径を大きくした中間部の筒体が接続され、該中
間部の筒体を小曲率でガイド支持する支持部材とを備え
ていることを特徴とする炉内中性子束検出器の案内装
置。
1. A guide tube through which a lower cylinder for guiding a neutron flux detector in a reactor is inserted into a fuel assembly in a nuclear reactor,
An upper core support plate that supports an upper core support column that supports the guide tube, and is established on a batch lifting plate in the reactor,
An instrumentation nozzle that penetrates the reactor vessel lid, an upper cylinder installed in an in-core instrumentation support column in the instrumentation nozzle, and an upper cylinder and the lower cylinder. Between the upper cylinder and the lower
A connecting member connected to an intermediate cylindrical body having a diameter larger than that of the cylindrical body and guiding and supporting the intermediate cylindrical body at a small curvature;
Guiding device in the furnace neutron flux detector, characterized by that.
JP30943992A 1992-10-23 1992-10-23 Guide device for neutron flux detector in reactor Expired - Lifetime JP3153833B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP30943992A JP3153833B2 (en) 1992-10-23 1992-10-23 Guide device for neutron flux detector in reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP30943992A JP3153833B2 (en) 1992-10-23 1992-10-23 Guide device for neutron flux detector in reactor

Publications (2)

Publication Number Publication Date
JPH06138283A JPH06138283A (en) 1994-05-20
JP3153833B2 true JP3153833B2 (en) 2001-04-09

Family

ID=17993014

Family Applications (1)

Application Number Title Priority Date Filing Date
JP30943992A Expired - Lifetime JP3153833B2 (en) 1992-10-23 1992-10-23 Guide device for neutron flux detector in reactor

Country Status (1)

Country Link
JP (1) JP3153833B2 (en)

Families Citing this family (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US9082519B2 (en) * 2008-12-17 2015-07-14 Westinghouse Electric Company Llc Upper internals arrangement for a pressurized water reactor
JP5606361B2 (en) * 2011-03-02 2014-10-15 三菱重工業株式会社 Guide device for neutron flux detector
JP5667937B2 (en) * 2011-07-01 2015-02-12 株式会社東芝 In-reactor inspection method
US9064607B2 (en) * 2012-04-27 2015-06-23 Westinghouse Electric Company Llc Method and apparatus for refueling a nuclear reactor having an instrumentation penetration flange
JP6244246B2 (en) * 2014-03-31 2017-12-06 株式会社日立製作所 Nuclear instrumentation piping for boiling water reactors
CN105632571A (en) * 2014-12-01 2016-06-01 上海核工程研究设计院 Integrated reactor equipment

Also Published As

Publication number Publication date
JPH06138283A (en) 1994-05-20

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