JPS612092A - Upper mechanism of core for fast breeder reactor - Google Patents
Upper mechanism of core for fast breeder reactorInfo
- Publication number
- JPS612092A JPS612092A JP59122652A JP12265284A JPS612092A JP S612092 A JPS612092 A JP S612092A JP 59122652 A JP59122652 A JP 59122652A JP 12265284 A JP12265284 A JP 12265284A JP S612092 A JPS612092 A JP S612092A
- Authority
- JP
- Japan
- Prior art keywords
- core
- control rod
- reactor
- instrumentation
- 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.)
- Granted
Links
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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ェル8を集束した
複数の計装ウェル案内管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 has a tube plate 10
By being fastened to the core 4, 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
材を隣接する伯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
体が万一浮上がった場合でも、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 separates the coolant flowing out from the fuel assembly from the coolant flowing out from the adjacent fuel assembly. 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
によって生ずる流体振動を起因とする計装つ■ル8の疲
労損傷を防止し、また計装ウェル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、胴
5下端の支持板6から垂下する計装ウェル案内管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ェル
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 prevents measurement of measurement sensors such as thermometers 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, and the tip of the instrumentation well 8 that has passed through the guide tube 9 is inside the sampling tube 11. is inserted into.
[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1
0と計装ウェル案内管9の構造が複雑化し、製作が困難
となる上、管板10.’7)重量が増加するため地震時
等における製御棒案内管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った。[Problems with the background art] In the conventional core upper mechanism configured as described above,
As the number of fuel assemblies composing the reactor core increases, the tube plate 1
0 and the instrumentation well guide tube 9 become complicated and difficult to manufacture, and the tube plate 10. '7) Due to the increased weight, the amount of displacement of the lower end of the control rod guide tube 7 during an earthquake or the like exceeds the allowable amount of displacement, which may reduce the insertion of the control rod.
[発明の目的]
本発明は上述の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 problems, and it is possible to improve the 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 that is simple and lightweight, easy to manufacture, and that can reduce the amount of displacement at the lower end of a control rod guide tube to ensure control rod insertability during earthquakes, etc. With the goal.
[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(
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、前記用の下部よ
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ェル挿入孔を形
成し、これらの計装ウェル挿入孔には前記炉心出口機器
の下端を貫通して配設したことを特徴とする。[Summary of the Invention] The upper core mechanism of the fast breeder reactor of the present invention penetrates a rotating plug that closes the upper opening of the reactor vessel, and the reactor core structure (
A control rod guide tube that houses a control rod drive mechanism in a cylindrical shell vertically installed above the fuel assembly, and a core outlet device that measures the temperature of the coolant flowing out from the fuel assembly. In the upper core mechanism for storing and deploying the fuel assemblies, a lattice-like member is suspended from the lower part of the reactor directly above the core, and an instrumentation well insertion hole is formed in this lattice-like member so as to be located at the center of the fuel assembly. The instrumentation well insertion hole is disposed through the lower end of the core outlet equipment.
[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である。In these figures, the same members as in FIGS. 4 and 5 are given 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ェル8を収束した複数の計装ウェ
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 core upper 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路を閉塞しないよう
細巾の仮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
計装ウェル挿入孔22が透設されている。2 and 3 show details of the lower part of the upper core mechanism 3 and the vicinity of the upper end of the core 4, and the lattice member 21 does not block the flow path of the coolant flowing out from each fuel assembly 30. It is constructed by assembling thin cloth temporary pieces in a lattice shape, and an instrumentation well insertion hole 22 is transparently provided directly above the center of the coolant outlet 31 of each fuel assembly 30.
これらの計装ウェル挿入孔22にはそれぞれ計装ウェル
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 passes through and is fixed in each of these instrumentation well insertion holes 22 .
以上のように構成されIC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ェル8の先端は、燃
料集合体30の冷却材出口31の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計測できる。In the upper core mechanism of the IC 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 to the fuel assembly 30. Since it is disposed directly above the coolant outlet 31 of the fuel assembly, the temperature of the coolant can be measured without mixing with the coolant flowing out from other adjacent fuel assemblies.
しかも計装ウェル8の先端部は格子状部材21に設けら
れた計装ウェル挿入孔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ェル案内管゛を取除い
た状態における計装ウェルと比較した場合、すなわち計
装ウェ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となるため計装ウェルが燃料集合
体から流出する冷却材によっ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って、
流体振動が発生する可能性がある場合には、計装ウェル
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, since the tip of the instrumentation well 8 is supported by penetrating the instrumentation well insertion hole 22 provided in the grid-like member 21, the instrumentation well guide tube of the conventional core upper mechanism is removed. When compared with the instrumentation well in , i.e. when the tip of the instrumentation well is supported and free,
Since the natural frequency is approximately 4=1, the instrumentation well will not experience fluid vibrations due to the coolant flowing out of the fuel assembly. In the unlikely event that coolant leaks from the fuel assembly,
If there is a possibility of fluid vibration occurring, this can be easily dealt with by slightly changing the outer diameter or wall thickness of the instrumentation well to increase its rigidity.
まl〔、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って抑制される。The lifting of the fuel assemblies is suppressed by a grid-like member placed 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、管板21と複数の制御棒案内管7および支持パイプ
20によって多点支持された格子状部材21によって拘
束される上、計装ウェル案内管9やサンプリング管11
の省略によっ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 tube plate 21, a plurality of control rod guide tubes 7, and the support pipes 20; Well guide tube 9 and sampling tube 11
By omitting this, the load on the control rod guide tube is reduced, so it becomes extremely small.
[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.
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図における計装ウェ
ル案内管近傍をを拡大しC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・・・・・・・・・計装ウェル
9・・・・・・・・・計装ウェル案内管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・・・・・・・・・計装ウェル挿入孔30・・・・
・・・・・燃料集合体
31・・・・・・・・・冷却材出口
策1図
第 2図
第 3 図
第4図
5図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. FIG. 5 is a vertical cross-sectional view illustrating the upper mechanism, and FIG. 5 is an enlarged vertical cross-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...Reactor core 5......Body 6...Support plate 7...Control rod guide tube 8...Instrumentation well 9...Instrumentation well guide pipe 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 plan Fig. 1 Fig. 2 Fig. 3 Fig. 4 Fig. 5
Claims (2)
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
計装ウェル挿入孔を形成し、これらの計装ウェル挿入孔
には前記炉心出口機器の下端を貫通して配設したことを
特徴とする高速増殖炉の炉心上部機構。(1) A control rod guide 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 tubes and core exit equipment for measuring the temperature of the coolant flowing out from the fuel assembly, a lattice-like member is suspended from the lower part of the shell directly above the core, and the lattice-like member is The member has an instrumentation well insertion hole formed in the center of the fuel assembly, and these instrumentation well insertion holes are provided so as to penetrate through the lower end of the core outlet equipment. Upper core mechanism of the reactor.
って胴に吊下げられていることを特徴とする特許請求の
範囲第1項記載の高速増殖炉の炉心上部機構。(2) The upper core mechanism of a fast breeder reactor according to claim 1, wherein the lattice-like member is suspended from the shell by a control rod guide tube and a support pipe.
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 true JPS612092A (en) | 1986-01-08 |
| JPH0548436B2 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) |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS54130788A (en) * | 1978-03-31 | 1979-10-11 | Toshiba Corp | Nuclear reactor |
-
1984
- 1984-06-14 JP JP59122652A patent/JPS612092A/en active Granted
Patent Citations (1)
| 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 |
|---|---|
| JPH0548436B2 (en) | 1993-07-21 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| LAPS | Cancellation because of no payment of annual fees |