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JPH0548436B2 - - Google Patents
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JPH0548436B2 - - Google Patents

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Publication number
JPH0548436B2
JPH0548436B2 JP59122652A JP12265284A JPH0548436B2 JP H0548436 B2 JPH0548436 B2 JP H0548436B2 JP 59122652 A JP59122652 A JP 59122652A JP 12265284 A JP12265284 A JP 12265284A JP H0548436 B2 JPH0548436 B2 JP H0548436B2
Authority
JP
Japan
Prior art keywords
core
control rod
instrumentation
reactor
fuel assembly
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 - Fee Related
Application number
JP59122652A
Other languages
Japanese (ja)
Other versions
JPS612092A (en
Inventor
Hatsuki Yamada
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
Tokyo Shibaura Electric Co 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 Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP59122652A priority Critical patent/JPS612092A/en
Publication of JPS612092A publication Critical patent/JPS612092A/en
Publication of JPH0548436B2 publication Critical patent/JPH0548436B2/ja
Granted 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)

Description

【発明の詳細な説明】 [発明の技術分野] 本発明は液体ナトリウムのような液体金属を冷
却材として使用する高速増殖炉の炉心上部機構に
関する。
DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to an upper core mechanism of a fast breeder reactor that uses a liquid metal such as liquid sodium as a coolant.

[発明の技術的背景] 一般に、液体ナトリウムを冷却材とする高速増
殖炉においては、運転監視や異常診断のため各燃
料集合体の出口部に温度計等の炉心出口計装を設
置し、これを炉心上部機構で支持する構造が採用
されている。
[Technical Background of the Invention] Generally, in fast breeder reactors that use liquid sodium as a coolant, core exit instrumentation such as a thermometer is installed at the exit of each fuel assembly for operation monitoring and abnormality diagnosis. A structure is adopted in which the core is supported by the upper core mechanism.

従来の高速増殖炉は、第4図に示すように、原
子炉容器1の上部開口部を回転プラグ2で閉塞さ
れており、この回転プラグに取付けた炉心上部機
構3は回転プラグを貫通し、その下端は原子炉容
器1内に設置された炉心4の上方に垂設されてい
る。
In the conventional fast breeder reactor, as shown in FIG. 4, the upper opening of the reactor vessel 1 is closed with a rotating plug 2, and the core upper mechanism 3 attached to this rotating plug passes through the rotating plug. Its lower end is suspended above the reactor core 4 installed in the reactor vessel 1 .

炉心上部機構3は円筒状の胴5内部に複数の支
持板6を設けられ、これに制御棒を保持駆動する
制御棒駆動機構(図示せず)を収納する複数の制
御棒案内管7と、温度計等を収納した多数の細管
状の計装ウエル8を集束した複数の計装ウエル案
内管9とを装着配備されている。
The upper core mechanism 3 is provided with a plurality of support plates 6 inside a cylindrical shell 5, and a plurality of control rod guide tubes 7 that accommodate control rod drive mechanisms (not shown) that hold and drive control rods. A plurality of instrumentation well guide tubes 9 are installed in which a large number of thin tube-shaped instrumentation wells 8 containing thermometers and the like are converged.

また炉心上部機構3の下部には、第5図に拡大
して示すように、各制御棒案内管7の下端近傍を
締結保持する管板10が設置されている。各制御
棒案内管7は管板10と締結されることにより、
曲げ剛性を高められ、収納した制御棒駆動機構の
地震時等における炉心4との相対変位を許容変位
量内に保たれる。
Further, in the lower part of the upper core mechanism 3, as shown in an enlarged view in FIG. 5, a tube plate 10 is installed which fastens and holds the vicinity of the lower end of each control rod guide tube 7. Each control rod guide tube 7 is fastened to the tube plate 10, so that
The bending rigidity is increased, and the relative displacement of the housed control rod drive mechanism with respect to the reactor core 4 during an earthquake or the like is maintained within the allowable displacement amount.

また、管板10は炉心4を構成する各燃料集合
体(図示せず)の真上に配備され、燃料集合体か
ら流出する冷却材を隣接する他の燃料集合体から
流出する冷却材と隔離して上方に導く円筒状のサ
ンプリング管11を保持している。これらのサン
プリング管11の下端には燃料集合体が万一浮上
がつた場合でも、それを一定範囲内に制限する突
起部12が取付けられている。
Further, the tube sheet 10 is disposed directly above each fuel assembly (not shown) constituting the reactor core 4, and isolates the coolant flowing out from the fuel assembly from the coolant flowing out from other adjacent fuel assemblies. It holds a cylindrical sampling tube 11 which is guided upward. Projections 12 are attached to the lower ends of these sampling tubes 11 to limit the floating of the fuel assembly within a certain range even if the fuel assembly should float.

サンプリング管11は、燃料集合体から流出す
る冷却材によつて生ずる流体振動を起因とする計
装ウエル8の疲労損傷を防止し、また計装ウエル
8の変動による温度計等の計測センサーの計測精
度の低下を防止するため、計装ウエル8は胴5下
端の支持板6から垂下する計装ウエル案内管9内
に収納されており、この案内管9内を貫通した計
装ウエル8の先端はサンプリング管11内に挿入
されている。
The sampling pipe 11 prevents fatigue damage to the instrumentation well 8 caused by fluid vibration caused by coolant flowing out from the fuel assembly, and also prevents measurement sensors such as a thermometer from measuring due to fluctuations in the instrumentation well 8. In order to prevent a decrease in accuracy, the instrumentation well 8 is housed in an instrumentation well guide tube 9 that hangs down from the support plate 6 at the lower end of the body 5. is inserted into the sampling tube 11.

[背景技術の問題点] 上述のように構成した従来の炉心上部機構にお
いては、炉心を構成する燃料集合体の本数が多く
なると、管板10と計装ウエル案内管9の構造が
複雑化し、製作が困難となる上、管板10の重量
が増加するため地震時等における制御棒案内管7
の下端変位量が許容変位量を上回り、制御棒の挿
入を低下させるおそれがあつた。
[Problems with Background Art] In the conventional upper core mechanism configured as described above, as the number of fuel assemblies configuring the core increases, the structure of the tube plate 10 and the instrumentation well guide tube 9 becomes complicated. In addition to being difficult to manufacture, the weight of the tube sheet 10 increases, so the control rod guide tube 7 is not suitable for earthquakes, etc.
The amount of displacement at the lower end of the rod exceeded the allowable amount of displacement, and there was a risk that the insertion of the control rod would be reduced.

[発明の目的] 本発明は上述の従来の問題点に鑑みてなされた
もので、炉心出口計装を対象とする燃料集合体の
本数が多い原子炉においても、炉心出口計装のた
めの構造の簡素化と軽量化を可能とし、製作が容
易であり、しかも制御棒案内管の下端変位量を低
減させて地震時等における制御棒挿入性を確保で
きる高速増殖炉の炉心上部機構を提供することを
目的とする。
[Object of the Invention] The present invention has been made in view of the above-mentioned conventional problems, and it provides a structure for core exit instrumentation even in a nuclear reactor with a large number of fuel assemblies targeted for core exit instrumentation. To provide an upper core mechanism for a fast breeder reactor, which is simple and lightweight, is easy to manufacture, and can reduce the amount of displacement of the lower end of a control rod guide tube to ensure control rod insertability during earthquakes, etc. The purpose is to

[発明の概要] 本発明の高速増殖炉の炉心上部機構は、原子炉
容器の上部開口部を閉塞する回転プラグを貫通
し、炉心を構成する燃料集合体の上方に垂設され
る円筒状の胴内に、制御棒駆動機構を収納する制
御棒案内管と、前記燃料集合体から流出する冷却
材の温度等を測定する炉心出口機器とを収納配備
する炉心上部機構において、前記胴の下部より炉
心真上に格子状部材を吊下げ、この格子状部材に
は燃料集合体の中心に位置するよう計装ウエル挿
入孔を形成し、これらの計装ウエル挿入孔には前
記炉心出口機器の下端が貫通し格子状部材から下
方に突出した状態で支持されることを特徴とす
る。
[Summary of the Invention] The upper core mechanism of the fast breeder reactor of the present invention has a cylindrical structure that penetrates a rotating plug that closes the upper opening of the reactor vessel and is suspended above the fuel assemblies that constitute the reactor core. In an upper core mechanism in which a control rod guide tube that accommodates a control rod drive mechanism and a core outlet device that measures the temperature, etc. of the coolant flowing out from the fuel assembly are housed in the shell, from the lower part of the shell. A grid-like member is suspended directly above the reactor core, and instrumentation well insertion holes are formed in this grid-like member so as to be located at the center of the fuel assembly. is characterized in that it is supported in a state where it penetrates and projects downward from the grid-like member.

[発明の実施例] 以下本発明の実施例を第1図、第2図および第
3図を参照して説明する。
[Embodiments of the Invention] Examples of the present invention will be described below with reference to FIGS. 1, 2, and 3.

なお、これらの図中、第4図、第5図における
と同一部材には同一の符号を付してある。
In these figures, the same members as in FIGS. 4 and 5 are designated by the same reference numerals.

第1図は本発明の炉心上部機構の縦断面図を示
している。同図において、炉心上部機構3は円筒
状の胴5を有し、この胴内には複数の支持板6が
設けられている。これらの支持板には制御棒駆動
機構を収納した複数の制御棒案内管7と、炉心出
口計装を行なう温度計等を収納した多数の細管状
の計装ウエル8を収束した複数の計装ウエル案内
管9とが装着されている。また、胴5の下端には
その周上に配設した複数の支持パイプ20を介し
て格子状部材21が吊下げられている。
FIG. 1 shows a longitudinal sectional view of the upper core mechanism of the present invention. In the figure, the upper core mechanism 3 has a cylindrical shell 5, and a plurality of support plates 6 are provided inside the shell. These support plates contain a plurality of control rod guide tubes 7 that house control rod drive mechanisms, and a plurality of instrumentation wells 8 that house thermometers and the like that perform core exit instrumentation. A well guide tube 9 is attached. Further, a lattice-like member 21 is suspended from the lower end of the body 5 via a plurality of support pipes 20 disposed around the circumference thereof.

第2図と、第3図は炉心上部機構3の下部と、
炉心4の上端近傍の詳細を示すもので、格子状部
材21は各燃料集合体30から流出する冷却材の
流炉を閉塞しないよう細巾の板を格子状に組立て
て構成されており、また、各燃料集合体30の冷
却材出口31の中心部真上部分には計装ウエル挿
入孔22が透設されている。
Figures 2 and 3 show the lower part of the upper core mechanism 3,
This figure shows the details of the vicinity of the upper end of the reactor core 4. The lattice member 21 is constructed by assembling narrow plates in a lattice shape so as not to block the flow furnace of coolant flowing out from each fuel assembly 30. , an instrumentation well insertion hole 22 is transparently provided directly above the center of the coolant outlet 31 of each fuel assembly 30.

これらの計装ウエル挿入孔22にはそれぞれ計
装ウエル8の先端近傍が貫通固定されている。
The vicinity of the tip of the instrumentation well 8 is passed through and fixed to each of these instrumentation well insertion holes 22 .

以上のように構成された本発明の炉心上部機構
においては、各燃料集合体30から流出する冷却
材の温度等を計測する温度計等を収納した計装ウ
エル8の先端は格子状部材21から下方に突出し
て、燃料集合体30の冷却材出口31のすぐ真上
に配備されているため、隣接する他の燃料集合体
から流出する冷却材との混合を生ずることなく冷
却材の温度等を正確に計測できる。
In the upper core mechanism of the present invention configured as described above, the tip of the instrumentation well 8 housing a thermometer etc. for measuring the temperature of the coolant flowing out from each fuel assembly 30 is connected from the grid member 21. Since it protrudes downward and is placed directly above the coolant outlet 31 of the fuel assembly 30, it is possible to maintain the temperature of the coolant without mixing with the coolant flowing out from other adjacent fuel assemblies. Can be measured accurately.

しかも計装ウエル8の先端部は格子状部材21
に設けられた計装ウエル挿入孔22を貫通して支
持されているため、従来の炉心上部機構の計装ウ
エル案内管を取除いた状態における計装ウエルと
比較した場合、すなわち計装ウエルの先端が支持
された場合と自由な場合とでは、固有振動数が約
4:1となるため計装ウエルが燃料集合体から流
出する冷却材によつて流体振動を生ずることはな
い。万一、燃料集合体より流出する冷却材によつ
て、流体振動が発生する可能性がある場合には、
計装ウエルの外径または肉厚を多少変更して剛性
を高めることにより容易に対応できる。
Moreover, the tip of the instrumentation well 8 is connected to the grid member 21.
Since the instrumentation well is supported by penetrating the instrumentation well insertion hole 22 provided in the Since the natural frequency is about 4:1 between supported and free tips, the instrumentation well does not experience fluid oscillations due to coolant exiting the fuel assembly. In the unlikely event that fluid vibrations may occur due to coolant flowing out of the fuel assembly,
This can be easily addressed by slightly changing the outer diameter or wall thickness of the instrumentation well to increase its rigidity.

また、燃料集合体の浮上がりは、それらの真上
に配置された格子状部材によつて抑制される。
Further, floating of the fuel assemblies is suppressed by the grid member disposed directly above them.

さらに、地震時等における制御棒案内管7の下
端変位量は、支持板6と複数の制御棒案内管7お
よび支持パイプ20によつて多点支持された格子
状部材21によつて拘束される上、計装ウエル案
内管9やサンプリング管11の省略によつて制御
棒案内管の負担荷重が軽減されるため、極めて少
なくなる。
Furthermore, the amount of displacement of the lower end of the control rod guide tube 7 during an earthquake or the like is restrained by the lattice member 21 supported at multiple points by the support plate 6, a plurality of control rod guide tubes 7, and the support pipes 20. Moreover, the load on the control rod guide tubes is reduced by omitting the instrumentation well guide tube 9 and the sampling tube 11, so that the load is extremely reduced.

[発明の効果] 以上の記載から明らかなように、本発明によれ
ば炉心出口計装の対象である燃料集合体の本数が
多い大型原子炉においても、炉心出口計装用機器
の構造、構成を簡素化、軽量化できるため、製作
が容易であり、また地震時等における制御棒案内
管の下端変位量を低減し得るので制御棒の挿入性
を確保でき、原子炉の安全性を向上させることが
できる。
[Effects of the Invention] As is clear from the above description, according to the present invention, even in large nuclear reactors with a large number of fuel assemblies targeted for core exit instrumentation, the structure and composition of the core exit instrumentation equipment can be improved. Because it can be simplified and lightweight, it is easy to manufacture, and the displacement of the lower end of the control rod guide tube during earthquakes can be reduced, ensuring ease of control rod insertion and improving the safety of the reactor. I can do it.

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

第1図は本発明の実施例を示す炉心上部機構の
縦断面図、第2図と第3図はそれぞれ本発明にお
ける格子状部材近傍の平面図と縦断面図、第4図
は従来の炉心上部機構を例示する縦断面図、第5
図は第2図における計装ウエル案内管近傍をを拡
大して示す縦断面図である。 1……原子炉容器、2……回転プラグ、3……
炉心上部機構、4……炉心、5……胴、6……支
持板、7……制御棒案内管、8……計装ウエル、
9……計装ウエル案内管、10……管板、11…
…サンプリング管、12……突起部、20……支
持パイプ、21……格子状部材、22……計装ウ
エル挿入孔、30……燃料集合体、31……冷却
材出口。
FIG. 1 is a vertical cross-sectional view of the upper core mechanism showing an embodiment of the present invention, FIGS. 2 and 3 are a plan view and a vertical cross-sectional view of the vicinity of the lattice member in the present invention, respectively, and FIG. 4 is a conventional core structure. Vertical sectional view illustrating the upper mechanism, No. 5
This figure is an enlarged vertical sectional view showing the vicinity of the instrumentation well guide tube in FIG. 2. 1... Reactor vessel, 2... Rotating plug, 3...
Core upper mechanism, 4... Core, 5... Shell, 6... Support plate, 7... Control rod guide tube, 8... Instrumentation well,
9...Instrumentation well guide tube, 10...Tube plate, 11...
... Sampling tube, 12 ... Protrusion, 20 ... Support pipe, 21 ... Grid member, 22 ... Instrumentation well insertion hole, 30 ... Fuel assembly, 31 ... Coolant outlet.

Claims (1)

【特許請求の範囲】[Claims] 1 原子炉容器の上部開口部を閉塞する回転プラ
グを貫通し、炉心を構成する燃料集合体の上方に
垂設される円筒状の胴内に、制御棒駆動機構を収
納する制御棒案内管と、前記燃料集合体から流出
する冷却材の温度等を測定する炉心出口機器とを
収納配備する炉心上部機構において、前記胴の下
部より炉心真上に格子状部材を吊下げ、この格子
状部材には燃料集合体の中心に位置するよう計装
ウエル挿入孔を形成し、これらの計装ウエル挿入
孔には前記炉心出口機器の下端が貫通し格子状部
材から下方に突出した状態で支持されることを特
徴とする高速増殖炉の炉心上部機構。
1. A control rod guide tube that houses a control rod drive mechanism in a cylindrical shell that penetrates a rotating plug that closes the upper opening of the reactor vessel and is vertically installed above the fuel assemblies that make up the reactor core. In the upper core mechanism that houses and deploys core outlet equipment for measuring the temperature of coolant flowing out from the fuel assembly, a lattice member is suspended directly above the core from the lower part of the shell, and a lattice member is suspended from the lower part of the shell, and instrumentation well insertion holes are formed to be located at the center of the fuel assembly, and the lower ends of the core outlet equipment pass through these instrumentation well insertion holes and are supported in a state protruding downward from the grid member. The upper core mechanism of a fast breeder reactor is characterized by:
JP59122652A 1984-06-14 1984-06-14 Upper mechanism of core for fast breeder reactor Granted JPS612092A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP59122652A JPS612092A (en) 1984-06-14 1984-06-14 Upper mechanism of core for fast breeder reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP59122652A JPS612092A (en) 1984-06-14 1984-06-14 Upper mechanism of core for fast breeder reactor

Publications (2)

Publication Number Publication Date
JPS612092A JPS612092A (en) 1986-01-08
JPH0548436B2 true JPH0548436B2 (en) 1993-07-21

Family

ID=14841274

Family Applications (1)

Application Number Title Priority Date Filing Date
JP59122652A Granted JPS612092A (en) 1984-06-14 1984-06-14 Upper mechanism of core for fast breeder reactor

Country Status (1)

Country Link
JP (1) JPS612092A (en)

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS54130788A (en) * 1978-03-31 1979-10-11 Toshiba Corp Nuclear reactor

Also Published As

Publication number Publication date
JPS612092A (en) 1986-01-08

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