JPS5997092A - Supporting device for neutron instrumentation guide tube - Google Patents

Supporting device for neutron instrumentation guide tube

Info

Publication number
JPS5997092A
JPS5997092A JP57206625A JP20662582A JPS5997092A JP S5997092 A JPS5997092 A JP S5997092A JP 57206625 A JP57206625 A JP 57206625A JP 20662582 A JP20662582 A JP 20662582A JP S5997092 A JPS5997092 A JP S5997092A
Authority
JP
Japan
Prior art keywords
guide tube
neutron instrumentation
instrumentation guide
group
tube group
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Pending
Application number
JP57206625A
Other languages
Japanese (ja)
Inventor
宮野 廣
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.)
Toshiba Corp
Original Assignee
Toshiba Corp
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 Toshiba Corp filed Critical Toshiba Corp
Priority to JP57206625A priority Critical patent/JPS5997092A/en
Publication of JPS5997092A publication Critical patent/JPS5997092A/en
Pending legal-status Critical Current

Links

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

Landscapes

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 〔発明の技術分野〕 本発明は沸騰水形原子炉の炉心下方に設けられた中性子
計装案内管の支持装置に関する。
DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a support device for a neutron instrumentation guide tube provided below the core of a boiling water nuclear reactor.

〔発明の技術的背景とその問題点〕[Technical background of the invention and its problems]

従来の沸騰水形原子炉の中性子計装案内管支持装置は、
炉心下部ゾレナム内において炉心シュラウド壁内に林立
する中性子計装案内管群を結合部材により格子状に一体
に結合して中性子計装案内管群全体の固有振動数を高め
各案内管の剛性を高めて冷却材の流れによる案内管の振
動を小さくするように構成されでいた。
The conventional boiling water reactor neutron instrumentation guide tube support device is
In the lower core solenum, the neutron instrumentation guide tubes that stand in a forest within the core shroud wall are connected together in a lattice shape using coupling members to increase the natural frequency of the entire neutron instrumentation guide tube group and increase the rigidity of each guide tube. The guide tube was constructed to reduce vibrations of the guide tube due to the flow of coolant.

ところが炉心下方における冷却材の流れ、特に圧力容器
の周壁面に沿って下部ゾレナム内に流入し中性子計装案
内管に直交して流れる冷却材の流速が大きくなると、中
性子計装案内管群を一体に結合しただけではそれらの振
動を十分に抑えられなくなることが予想され、その対策
として結合部材の端部を炉心シュラウド壁に固定し、剛
性の一層の向上をはかることが考えられている。
However, as the flow rate of the coolant below the reactor core increases, especially the flow rate of the coolant that flows into the lower solenum along the peripheral wall of the pressure vessel and flows perpendicularly to the neutron instrumentation guide tubes, the neutron instrumentation guide tubes become integrated. It is predicted that these vibrations will not be suppressed sufficiently by simply connecting the connecting member to the core shroud, and as a countermeasure, it is being considered to fix the end of the connecting member to the core shroud wall in order to further improve the rigidity.

しかしこの場合、原子炉運転時では計装案内管周辺部の
冷却材が高温となっているため結合部材に熱膨張が生じ
て案内管群の格子にひずみが生じ、かつ熱応力が増大す
る問題があった。
However, in this case, during reactor operation, the coolant around the instrumentation guide tubes is at a high temperature, so thermal expansion occurs in the connecting members, causing distortion in the lattice of the guide tube group, and increasing thermal stress. was there.

〔発明の目的〕[Purpose of the invention]

本発明はこのような事情にもとづいてなされたもので、
その目的は、中性子計装案内管群を結合部材で格子状に
結合して剛性を高め、冷却材の流れによる。振動を小さ
くするとともに、結合部材の熱膨張による格子のひずみ
や熱応力の増大による破損を防止できる中性子計装案内
管支持装置を提供することにある。
The present invention was made based on these circumstances, and
The purpose is to increase rigidity by connecting the neutron instrumentation guide tube group in a lattice shape with connecting members, and to increase the rigidity due to the flow of coolant. It is an object of the present invention to provide a neutron instrumentation guide tube support device that can reduce vibration and prevent damage due to distortion of the lattice due to thermal expansion of coupling members and increase in thermal stress.

〔発明の概要〕[Summary of the invention]

本発明の中性子計装案内管支持装置は、炉心シュラウド
壁内に林立する中性子計装案内管群を少なくとも中心部
の案内管群と、これを囲む周辺部の案内管群とに区分け
して、その中心部および周辺部の案内管群を結合部材を
一部して群ごとに独立に格子状に結合し、その周辺部の
案内管群を結合する結合部材の一部のみを炉心シュラウ
ド°壁に固定して構成されている。
The neutron instrumentation guide tube support device of the present invention divides a group of neutron instrumentation guide tubes arranged in a core shroud wall into at least a central guide tube group and a peripheral guide tube group surrounding this, The guide tube groups at the center and the periphery are connected independently in a lattice shape for each group using some connecting members, and only a part of the connecting member connecting the guide tube groups at the periphery is connected to the core shroud wall. It is configured in a fixed manner.

〔発明の実施例〕[Embodiments of the invention]

以下、図面に示す一実施例にもとづいて説明する。 Hereinafter, a description will be given based on an embodiment shown in the drawings.

第1図は中性子計装案内管が設置される沸騰水形原子炉
下部ブレナム部を示すものである。
Figure 1 shows the lower blenum section of the boiling water reactor where the neutron instrumentation guide tube is installed.

すなわち原子炉圧力容器1の内部には、炉心2を構成す
るシーラウド壁3で囲まれた下部ゾレナムがあシ、ここ
には原子炉圧力容器1の周壁とシュラウド壁3との間(
設けられたインターナルポンf4・・・によりて冷却材
が送シ込まれる。
That is, inside the reactor pressure vessel 1, there is a lower solenum surrounded by the searoud wall 3 that constitutes the reactor core 2, and there is a space between the peripheral wall of the reactor pressure vessel 1 and the shroud wall 3 (
Coolant is pumped in by the provided internal pump f4.

また下部プレナムには炉心2の中性子量を測定する中性
子量を内蔵した多数の中性子計装案内管5・・・が、制
御棒(図示せず)と共に林立配置されている。これらの
中性子計装案内管5・・・は1段または複数段に組立て
られた帯板状の結合部材6・・・によシ結合されている
。上記結合部材6は、第2図に示すように、互いに格子
状に連結され、剛性が高められている。
Further, in the lower plenum, a large number of neutron instrumentation guide tubes 5 containing built-in neutrons for measuring the neutrons of the reactor core 2 are arranged in a forest together with control rods (not shown). These neutron instrumentation guide tubes 5 are connected by band-like connecting members 6 assembled in one or more stages. As shown in FIG. 2, the coupling members 6 are connected to each other in a lattice shape to increase rigidity.

また、中性子計装案内管5・・・は第2図(第1図の■
−■線に沿う断面図)に示すように、中心部の案内管群
5Aと周辺部の案内管群5Bに区分けされ、各群ごとに
独立に格子状に結合されているものである。なお、第2
図中7・・・は炉心2を構成する燃料集合体を模式的に
示すものである。
In addition, the neutron instrumentation guide tube 5... is shown in Figure 2 (■ in Figure 1).
As shown in the cross-sectional view taken along the line -■, the tube is divided into a guide tube group 5A in the center and a guide tube group 5B in the periphery, and each group is independently connected in a grid pattern. In addition, the second
7 in the figure schematically shows fuel assemblies that constitute the reactor core 2. In FIG.

案内管5・・・同志の結合は第3図の如く行なわれる。The guide tubes 5 are connected to each other as shown in FIG.

すなわち中央を半円状に曲成した1対の継手8,8で案
内管5を挾み、この側継手8゜8の端部間で前記結合部
材6の端部を挾んで王者を一体にボルト、リベット等の
固定具9で締付は固定する。
That is, the guide tube 5 is sandwiched between a pair of joints 8, 8 whose center is curved into a semicircular shape, and the ends of the connecting member 6 are held between the ends of the side joints 8°8 to unite the king. Tightening is done using a fixing device 9 such as a bolt or rivet.

そして周辺部の案内管群5Bについては、最端部の結合
部材6の一部がその端部をシュラウド壁3に溶接によっ
て固定されているが、−直線状に結合された複数の結合
部材6・・・の両端ともシュラウド壁3に固定されるこ
とはないように配慮されている。これは結合部材6・・
・の少なくとも一端側を自由にすることにより、その熱
膨張による応力増加を緩和するだめである。
Regarding the peripheral guide tube group 5B, a part of the connecting members 6 at the end end is fixed to the shroud wall 3 by welding, but - a plurality of connecting members 6 connected in a straight line . . is designed so that neither end thereof is fixed to the shroud wall 3. This is connecting member 6...
By leaving at least one end side free, the increase in stress due to thermal expansion can be alleviated.

また中心部の案内管群5Aについては、いずれの結合部
材6もシュラウド壁3に固定されていない。
Furthermore, for the central guide tube group 5A, none of the coupling members 6 is fixed to the shroud wall 3.

以上の如く構成することによシ次のような作用効果を得
ることができる。
By configuring as described above, the following effects can be obtained.

すなわち炉心下部プレナム内における冷却材の流量増加
によシ、下部プレナム内に林立する中性子計装案内管5
・・・には強い側圧が作用する。
In other words, due to an increase in the flow rate of coolant in the lower core plenum, the neutron instrumentation guide pipes 5 that stand in the lower plenum
Strong lateral pressure acts on...

この側圧は周辺部はど強く、下部プレナム中心部に近づ
くに従って、案−内管5・・・及び制御棒によシ緩和さ
れることになる。
This side pressure is strong at the periphery, and as it approaches the center of the lower plenum, it is relieved by the guide tubes 5 and the control rods.

ところで、周辺部の案内管5・・・は結合部材6・・・
によって格子状に結合されて一体の案内管群5Bを構成
し、しかも結合部材6・・・の一部がシーラウド壁3に
固定された結果、その案内管群5Bの剛性は十分高めら
れているので、冷却材の流れによる強い側圧を受けても
案内管5・・・の振動は小さく抑えられることになる。
By the way, the guide tube 5 in the peripheral part is connected to the connecting member 6...
are connected in a lattice shape to form an integrated guide tube group 5B, and as a result of a part of the connecting members 6 being fixed to the sea loud wall 3, the rigidity of the guide tube group 5B is sufficiently increased. Therefore, even if the guide tubes 5 receive strong lateral pressure due to the flow of coolant, the vibrations of the guide tubes 5 can be suppressed to a small level.

また結合部材6・・・に熱膨張が生じても、中心部の案
内管5・・・には結合されておらす、しかも−直線状に
結合された複数の結合部材6・・・の、少なくとも一端
が自由になっているの鞭、結合部材6・・・の熱応力は
小さく抑えられ、案内管5・・・は勿論、結合部材6・
・・にもひずみや破断を生じることはない。
Furthermore, even if thermal expansion occurs in the coupling members 6..., the plurality of coupling members 6..., which are coupled in a straight line, are still coupled to the central guide tube 5... Since at least one end is free, the thermal stress of the coupling member 6 can be suppressed to a low level, and the guide tube 5 as well as the coupling member 6 can be kept to a minimum.
... will not cause any distortion or breakage.

一方、中心部の案内管5・・・も結合部材6・・・によ
って格子状に結合されて一体の案内管1群5Aを構成す
ることによシ剛性が高められているので、冷却材の流れ
による振動を小さく抑えることができる。なお、中心部
の案内管群5Aはシーラウド壁3に固定されていないの
で周辺部の案内管群5Aによシは剛性が低いが、先に述
べた如く中心部では冷却材の流れによる側圧が周辺部よ
り弱いので、案内管群5Aの振動を十分小さく抑えるこ
とができる。またシュラウド壁3に固定されていないの
で熱応力も小さく抑えられ、案内管5・・・や結合部材
6・・・にびずみ、破断等を生ずるおそれはない。
On the other hand, the guide tubes 5 in the center are also connected in a lattice shape by the connecting members 6 to form an integrated guide tube group 5A, thereby increasing the rigidity of the guide tubes, so that the coolant can be Vibrations caused by the flow can be suppressed to a small level. Note that since the guide tube group 5A in the center is not fixed to the sea loud wall 3, it has lower rigidity than the guide tube group 5A in the peripheral area, but as mentioned earlier, the lateral pressure due to the flow of coolant is generated in the center. Since it is weaker than the peripheral portion, the vibration of the guide tube group 5A can be suppressed to a sufficiently low level. Furthermore, since they are not fixed to the shroud wall 3, thermal stress can be suppressed to a low level, and there is no risk of distortion, breakage, etc. occurring in the guide tubes 5 and the coupling members 6.

なお本発明は上記実施例に限定すべきものではない。た
とえば中性子計装案内管を中心部と、周辺部と、その中
間部の3つの案内管群に区分けしてもよい。
Note that the present invention should not be limited to the above embodiments. For example, the neutron instrumentation guide tube may be divided into three guide tube groups: a central portion, a peripheral portion, and an intermediate portion.

〔発明の効果〕〔Effect of the invention〕

以上詳述したように、本発明に係る中性子計装案内管支
持装置は、中性子計装案内管を少なくとも中心部の案内
管群と周辺部の案内管群とに区分けして、それぞれの案
内管群ごとに結合部材を介して独立に格子状に結合し、
周辺部の案内管群を結合する結合部材の一部のみを炉心
シュラウド壁に固定して一構成される。したがって案内
管の剛性が高められ、冷却材の流れによる振動を小さく
抑えることができるとともに、結合部材の熱膨張による
ひずみゃ破損を防止できるなど、所期の効果を奏するこ
とができる。
As described above in detail, the neutron instrumentation guide tube support device according to the present invention divides the neutron instrumentation guide tube into at least a center guide tube group and a peripheral guide tube group, and Each group is independently connected in a lattice shape via a connecting member,
One structure is constructed by fixing only a part of the connecting member that connects the peripheral guide tube group to the core shroud wall. Therefore, the rigidity of the guide tube is increased, vibrations caused by the flow of the coolant can be suppressed to a small level, and desired effects such as being able to prevent damage due to strain caused by thermal expansion of the connecting member can be achieved.

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

図は本発明の一実施例を示すもので、第1図は沸騰水形
原子炉の下部プレナム周辺部の縦断面図、第2図は第1
図の■−汀線に沿う断面図、第3図は結合部材と中性子
計装案内管との結合部を示す平面図である。 1・・・原子炉圧力容器、2・・・炉心、3・・・シュ
ラウド壁、4・・・ポンプ、5・・・中性子計装案内管
、5A 、5B・・・案内管群、6・・・結合部材。 出願人代理人  弁理士 鈴 江 武 彦牙1図 牙2図 第3図
The figures show one embodiment of the present invention, in which Figure 1 is a vertical cross-sectional view of the area around the lower plenum of a boiling water reactor, and Figure 2 is a vertical cross-sectional view of the area around the lower plenum of a boiling water reactor.
FIG. 3 is a cross-sectional view taken along the shoreline ``■'' in the figure, and FIG. 3 is a plan view showing the connecting portion between the connecting member and the neutron instrumentation guide tube. DESCRIPTION OF SYMBOLS 1... Reactor pressure vessel, 2... Reactor core, 3... Shroud wall, 4... Pump, 5... Neutron instrumentation guide tube, 5A, 5B... Guide tube group, 6... ...Connection member. Applicant's agent Patent attorney Takeshi Suzue Hikoga 1 Figure 2 Figure 3

Claims (1)

【特許請求の範囲】[Claims] 炉心シュラウド壁内に林立する中性子計装案内管群を少
なくとも中心部の案内管群と、これを囲む周辺部の案内
管群とに区分けして、その中心部および周辺部の案内管
群を結合部材を介して各群ごとに独立に格子状に結合し
、その周辺部の案内管群を結合する結合部材の一部のみ
を炉心シュラウド壁に固定したことを特徴とする中性子
計装案内管支持装置。
The neutron instrumentation guide tube group that stands in the core shroud wall is divided into at least a central guide tube group and a peripheral guide tube group surrounding this, and the central and peripheral guide tube groups are combined. A neutron instrumentation guide tube support characterized in that each group is independently connected in a lattice shape through members, and only a part of the connecting member that connects guide tube groups in the peripheral part is fixed to a core shroud wall. Device.
JP57206625A 1982-11-25 1982-11-25 Supporting device for neutron instrumentation guide tube Pending JPS5997092A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57206625A JPS5997092A (en) 1982-11-25 1982-11-25 Supporting device for neutron instrumentation guide tube

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57206625A JPS5997092A (en) 1982-11-25 1982-11-25 Supporting device for neutron instrumentation guide tube

Publications (1)

Publication Number Publication Date
JPS5997092A true JPS5997092A (en) 1984-06-04

Family

ID=16526467

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57206625A Pending JPS5997092A (en) 1982-11-25 1982-11-25 Supporting device for neutron instrumentation guide tube

Country Status (1)

Country Link
JP (1) JPS5997092A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS62259089A (en) * 1986-05-02 1987-11-11 株式会社日立製作所 Vibration control equipment for aggregate structure in fluid

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS62259089A (en) * 1986-05-02 1987-11-11 株式会社日立製作所 Vibration control equipment for aggregate structure in fluid
JPH0463355B2 (en) * 1986-05-02 1992-10-09 Hitachi Ltd

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