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JPH0520719B2 - - Google Patents
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JPH0520719B2 - - Google Patents

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Publication number
JPH0520719B2
JPH0520719B2 JP62229461A JP22946187A JPH0520719B2 JP H0520719 B2 JPH0520719 B2 JP H0520719B2 JP 62229461 A JP62229461 A JP 62229461A JP 22946187 A JP22946187 A JP 22946187A JP H0520719 B2 JPH0520719 B2 JP H0520719B2
Authority
JP
Japan
Prior art keywords
instrumentation tube
core
reactor
support plate
instrumentation
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
JP62229461A
Other languages
Japanese (ja)
Other versions
JPS6473297A (en
Inventor
Junichi Kaneko
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 JP62229461A priority Critical patent/JPS6473297A/en
Publication of JPS6473297A publication Critical patent/JPS6473297A/en
Publication of JPH0520719B2 publication Critical patent/JPH0520719B2/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

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  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 〔発明の目的〕 (産業上の利用分野) 本発明は原子炉炉心に装荷される炉内計装管に
係り、特に炉心への支持構造部を改良した炉内計
装管に関する。
[Detailed Description of the Invention] [Object of the Invention] (Industrial Application Field) The present invention relates to an in-core instrumentation tube loaded in a nuclear reactor core, and particularly relates to an in-core instrumentation tube with an improved support structure for the reactor core. Regarding piping.

(従来の技術) 従来よく知られているように、原子炉ではその
安全性監視、燃料の健全性維持およびその効率的
燃焼を達成するために、炉心内に中性子源領域モ
ニタ(SRM)、中間領域モニタ(IRM)、極部領
域出力モニタ(LPRM)等の中性子計装系の検
出器(以下中性子検出器という)が炉内計装管に
収納して分散配置され、炉心各部の出力部分が監
視される。このような炉内計装管は中性子検出器
の寿命、炉内計装管自体の照射寿命等を考慮し、
定期検査の際に順次計画的に交換される。
(Prior Art) As is well known in the past, nuclear reactors are equipped with a neutron source region monitor (SRM), intermediate Detectors of the neutron instrumentation system (hereinafter referred to as neutron detectors) such as the area monitor (IRM) and the polar area output monitor (LPRM) are housed in the in-core instrumentation tube and are distributed, and the output parts of each part of the reactor core are be monitored. This type of in-core instrumentation tube is designed with consideration to the lifespan of the neutron detector, the irradiation life of the in-core instrumentation tube itself, etc.
They are replaced in a planned manner during periodic inspections.

このような炉内計装管の従来例を第7図〜第1
0図に示している。
Conventional examples of such in-furnace instrumentation tubes are shown in Figures 7 to 1.
It is shown in Figure 0.

第7図に示すように、炉内計装管1は中空長尺
な計装管本体2を有し、この計装管本体2内に中
性子検出器(図示せず)を収納している。沸騰水
型原子炉の場合、炉内計装管1は原子炉圧力容器
3の炉心4に垂直に装荷され、その一端部(上端
部)は炉心支持板部としての上部格子板5aに支
持され、他端(下端)は下方の炉心支持板部であ
る炉心支持板5bを貫通して原子炉圧力容器3の
底部に設けたインコアハウジング6およびインコ
アフランジ7に支持される。
As shown in FIG. 7, the in-core instrumentation tube 1 has a hollow and elongated instrumentation tube body 2, and a neutron detector (not shown) is housed within the instrumentation tube body 2. As shown in FIG. In the case of a boiling water reactor, the in-core instrumentation tube 1 is loaded vertically into the core 4 of the reactor pressure vessel 3, and one end (upper end) thereof is supported by an upper grid plate 5a serving as a core support plate. , the other end (lower end) passes through a core support plate 5b, which is a lower core support plate part, and is supported by an in-core housing 6 and an in-core flange 7 provided at the bottom of the reactor pressure vessel 3.

第8図は炉内計装管1の上端部の支持構造、第
9図は下端部の支持構造をそれぞれ示している。
FIG. 8 shows the support structure for the upper end of the in-core instrumentation tube 1, and FIG. 9 shows the support structure for the lower end.

第8図に示すように、計装管本体2の上端部に
は圧接部8が設けられている。この圧接部8は計
装管本体2に摺動可能に嵌合した支持管9とこの
支持管9を上方に向つて付勢する圧縮コイルスプ
リング10とからなつている。支持管9の上端部
には大径部11が形成され、この大径部11が上
部格子板5aの下面に設けた窪み12に圧縮コイ
ルスプリング10の弾性力によつて圧入されてい
る。
As shown in FIG. 8, a pressure contact portion 8 is provided at the upper end portion of the instrumentation tube main body 2. As shown in FIG. The pressure contact portion 8 is comprised of a support tube 9 slidably fitted into the instrumentation tube main body 2 and a compression coil spring 10 that urges the support tube 9 upward. A large diameter portion 11 is formed at the upper end of the support tube 9, and the large diameter portion 11 is press-fitted into a recess 12 provided on the lower surface of the upper lattice plate 5a by the elastic force of a compression coil spring 10.

また、第9図に示すように、計装管本体2の下
端部には下方に向つて次第に小径となるテーパ部
13が形成されており、このテーパ部13がイン
コアフランジ7に形成したテーパ状の座14に圧
接している。この圧接力は炉内計装管1の自重お
よび圧縮コイルスプリング10の弾性力さらに炉
水圧等によつて得られ、炉水の洩れを十分に防止
するシール作用をテーパ部13および座14に与
える。なお、インコアハウジング6は原子炉圧力
容器3の底部に溶接等によつて一体的に固着して
設けられ、インコアフランジ7はインコアハウジ
ング6にボルト等の締付け具15によつて固定さ
れる。
Further, as shown in FIG. 9, a tapered portion 13 is formed at the lower end of the instrumentation tube main body 2, and the diameter gradually decreases toward the bottom. It is in pressure contact with the seat 14. This pressure contact force is obtained by the weight of the in-core instrumentation tube 1, the elastic force of the compression coil spring 10, the reactor water pressure, etc., and provides the tapered portion 13 and the seat 14 with a sealing action that sufficiently prevents leakage of reactor water. . The in-core housing 6 is integrally fixed to the bottom of the reactor pressure vessel 3 by welding or the like, and the in-core flange 7 is fixed to the in-core housing 6 with fasteners 15 such as bolts.

第7図および第10図は、このような炉内計装
管1の炉心4への着脱作用を示している。
7 and 10 show the operation of attaching and detaching the in-core instrumentation tube 1 to and from the reactor core 4. As shown in FIG.

装着時にはまず第10図Aに示すように、天井
クレーン16によつて炉内計装管1を吊り降す。
そして同図Bに示すように、上部格子板5aの隙
間および炉心支持板5bの貫通孔17を介して炉
内計装管1の下端部をインコアハウジング6に挿
入する。その後同図Cに示すように、燃料交換機
18および治具19を使用して炉内計装管1を把
持し、同図Dに示すように、上部格子板5aの窪
み12に炉内計装管1の圧接部8を挿入する。な
お、この窪み12への圧接部8の挿入時には、治
具19によつて圧縮コイルスプリング10の弾性
力に抗して支持管9を一端押し下げ、大径部11
を窪み12に位置決めした後、その治具19を開
放することにより行なわれる。
When installing, first, as shown in FIG. 10A, the in-core instrumentation pipe 1 is suspended by the overhead crane 16.
Then, as shown in Figure B, the lower end of the in-core instrumentation tube 1 is inserted into the in-core housing 6 through the gap in the upper grid plate 5a and the through hole 17 in the core support plate 5b. Thereafter, as shown in FIG. Insert the pressure contact part 8 of the tube 1. Note that when inserting the pressure contact portion 8 into the recess 12, the support tube 9 is pushed down at one end by the jig 19 against the elastic force of the compression coil spring 10, and the large diameter portion 11
This is done by positioning the jig 19 in the recess 12 and then opening the jig 19.

(発明が解決しようとする問題点) 上述した従来の炉内計装管では、計装管本体の
一端(上端)を炉心支持板部である上部格子板5
aに圧接するための圧接部8が支持管9および圧
縮コイルスプリング10等によつて構成されてい
る。このため、圧接部8の構成が複雑であり、部
品点数の多いものとなつている。また、長時間の
使用によつて、支持管9の上端部の大径部11が
上部格子板5aの窪み12に固着したり、圧縮コ
イルスプリング10が変質する等の理由により、
支持管9が上部格子板5aに圧着固定される、い
わゆるステイツク状態となり、前述した装着時と
逆の取り外し操作を行なえなくなり、計装管本体
2を切断装置で切断する必要が生じる等の問題も
ある。
(Problems to be Solved by the Invention) In the conventional in-core instrumentation tube described above, one end (upper end) of the instrumentation tube body is connected to the upper grid plate 5 which is the core support plate.
A pressure contact portion 8 for pressure contact with a is constituted by a support tube 9, a compression coil spring 10, and the like. For this reason, the configuration of the pressure contact portion 8 is complicated and includes a large number of parts. In addition, due to long-term use, the large diameter portion 11 at the upper end of the support tube 9 may become stuck to the recess 12 of the upper lattice plate 5a, the compression coil spring 10 may deteriorate, etc.
The support tube 9 is crimped and fixed to the upper grid plate 5a, resulting in a so-called stuck state, which makes it impossible to perform the removal operation opposite to the above-mentioned mounting operation, and there are also problems such as the need to cut the instrumentation tube body 2 with a cutting device. be.

本発明はこのような事情に鑑みてなされたもの
で、圧接部の構造が簡単で、かつ部品点数の減少
も図れ、さらに炉心への着脱が容易かつ確実に行
なえて、ステイツク等の問題も生じない炉内計装
管を提供することを目的とする。
The present invention has been developed in view of these circumstances, and it is possible to simplify the structure of the pressure welding part, reduce the number of parts, and furthermore, it can be easily and reliably attached to and detached from the reactor core, eliminating problems such as static. The purpose is to provide an in-furnace instrumentation tube that does not require an in-core instrumentation tube.

〔発明の構成〕[Structure of the invention]

(問題点を解決するための手段) 本発明は、中空長尺な計装管本体内に中性子検
出器を収納し、その計装管本体の一端に設けた圧
接部を炉心支持板部に当接させて原子炉内に装荷
する炉内計装管において、前記圧接部を形状記憶
合金製とし、原子炉運転時の高温下で拡張すると
ともに原子炉停止時の低温下で収縮する形状記憶
を付与したことを特徴とする。
(Means for Solving the Problems) The present invention houses a neutron detector in a hollow, long instrumentation tube body, and brings a press-contact portion provided at one end of the instrumentation tube body into contact with a core support plate portion. In the in-core instrumentation tube that is placed in contact with the reactor and loaded into the reactor, the pressure-welded part is made of a shape memory alloy, which has a shape memory that expands under high temperatures during reactor operation and contracts under low temperatures when the reactor is shut down. It is characterized by being given.

(作 用) 本発明に係る炉内計装管によれば、圧接部を形
状記憶合金製とし、その圧接部は低温下で収縮し
高温下で拡張する形状記憶を付与したものである
から、炉内計装管の装着時や交換時等の原子炉停
止時における低温状態では炉心支持板部等に形成
される支持用の窪み等に対して緩んだ状態とな
り、炉内計装管着脱作用が自由にかつ確実に行な
える。また、原子炉運転時における高温下では、
形状記憶効果によつて圧接部が拡張するので、そ
の拡張作用によつて支持用の窪み等に圧接し、炉
心に確実に固定されるようになる。
(Function) According to the in-furnace instrumentation tube according to the present invention, the pressure welded portion is made of a shape memory alloy, and the pressure welded portion is given shape memory that contracts at low temperatures and expands at high temperatures. In low-temperature conditions when the reactor is shut down, such as when installing or replacing the in-core instrumentation tube, it becomes loose relative to the supporting depressions formed in the core support plate, etc., and the in-core instrumentation tube attachment and detachment are difficult. can be done freely and reliably. In addition, under high temperatures during reactor operation,
Since the press-contact portion expands due to the shape memory effect, the expansion action causes the press-contact portion to come into pressure contact with a support depression, etc., and is securely fixed to the reactor core.

したがつて、従来のような支持管や圧縮コイル
スプリング等を用いる必要がなく、構成が簡単
で、かつ部品点数が減少する。また、形状記憶効
果は確実であるから、圧接部が支持板部に固着す
るステイツク等の事態は発生しない。
Therefore, there is no need to use support tubes, compression coil springs, etc. as in the prior art, and the structure is simple and the number of parts is reduced. In addition, since the shape memory effect is reliable, a situation such as sticking of the pressure contact portion to the support plate portion does not occur.

(実施例) 以下、本発明の一実施例を第1図〜第6図を参
照して説明する。
(Example) An example of the present invention will be described below with reference to FIGS. 1 to 6.

第1図は沸騰水型原子炉の原子炉圧力容器21
の炉心22に炉内計装管23を装荷し、その炉心
22が原子炉運転によつて高温となつた状態を示
している。第1図に示すように、この実施例にお
いても炉内計装管23は中空長尺な計装管本体2
4内に中性子検出器を収納し、その計装管本体2
4の一端(上端)に設けた圧接部25を炉心支持
板部である上部格子板26に当接させるととも
に、その計装管本体24の他端(下端)を炉心支
持板27を通してインコアハウジング28および
インコアフランジ29の座30にテーパ部31を
密接させている。
Figure 1 shows the reactor pressure vessel 21 of a boiling water reactor.
The reactor core 22 is loaded with in-core instrumentation tubes 23, and the reactor core 22 is shown to be at a high temperature due to reactor operation. As shown in FIG. 1, in this embodiment as well, the in-core instrumentation tube 23 is a hollow long instrumentation tube main body 2.
A neutron detector is housed in the instrumentation tube body 2.
4 is brought into contact with the upper lattice plate 26 which is the core support plate part, and the other end (lower end) of the instrumentation tube body 24 is passed through the core support plate 27 to in-core housing 28. The tapered portion 31 is brought into close contact with the seat 30 of the in-core flange 29.

このものにおいて、圧接部25は計装管本体2
4の外周面に嵌合固着した形状記憶合金製の冠状
部品としている。即ち、この圧接部25としての
冠状部品は、筒状の基部25aとその一端部から
突出した複数本のアーム部25bとを有し、この
各アーム部25bを形状記憶効果によつて径方向
に拡張および収縮するものとしている。なお、ア
ーム部25bの先端にはそれぞれローラ25cを
回転自在に設けている。アーム部25bの形状記
憶効果は、原子炉運転時の高温下で拡張し、原子
炉停止時の低温下で収縮するものとしている。こ
れにより第1図に示す原子炉運転状態下ではアー
ム部25bが径方向に拡張し、上部格子板26の
下面に設けた窪み32にローラ25cを介して圧
接した状態となつている。
In this thing, the pressure contact part 25 is the instrumentation pipe main body 2
It is a crown-shaped part made of a shape memory alloy that is fitted and fixed to the outer circumferential surface of 4. That is, the crown-shaped component serving as the pressure contact portion 25 has a cylindrical base portion 25a and a plurality of arm portions 25b protruding from one end thereof, and each of the arm portions 25b is radially moved by the shape memory effect. It is supposed to expand and contract. Note that a roller 25c is rotatably provided at each end of the arm portion 25b. The shape memory effect of the arm portion 25b is such that it expands under high temperatures during nuclear reactor operation and contracts under low temperatures when the nuclear reactor is shut down. As a result, under the operating state of the reactor shown in FIG. 1, the arm portion 25b expands in the radial direction and is in pressure contact with the recess 32 provided on the lower surface of the upper lattice plate 26 via the roller 25c.

第2図はこのような圧接部25を有する炉内計
装管23の上端部の構成を拡大して示し、第3図
は同じくその平面形状を示し、さらに第4図は上
部格子板26全体の平面形状を示している。
FIG. 2 shows an enlarged view of the structure of the upper end of the in-core instrumentation tube 23 having such a pressure contact part 25, FIG. 3 also shows its planar shape, and FIG. 4 shows the entire upper grid plate 26. It shows the planar shape of .

第2図〜第4図に示すように上部格子板26の
炉内計装管装着位置に該当する交差部分には、圧
接部25当接用の窪み32の中心部と連通する挿
通孔33を穿設している。そして、計装管本体2
4は、圧接部25のさらに先端部(上端側)に環
状のガイド部34を備えたものとし、そのガイド
部34を挿通孔33の内周面に摺接させている。
このガイド部34には、第3図に示すように、圧
接部25のアーム部25bと周方向に45゜角度を
異ならせて回転防止用のピン35を90゜間隔で突
設している。この各ピン35は上部格子板26の
挿通孔33に面する両側隅角部に当接し、これに
より計装管本体24の回転を防止し、圧接部25
のアーム部25bが上部格子板26の窪み32か
ら外れることを防止している。
As shown in FIGS. 2 to 4, an insertion hole 33 is provided at the intersection of the upper grid plate 26 corresponding to the installation position of the in-furnace instrumentation tube, which communicates with the center of the recess 32 for abutting the pressure welding part 25. It is drilled. Then, the instrumentation tube body 2
No. 4 is provided with an annular guide portion 34 at the distal end (upper end side) of the pressure contact portion 25, and the guide portion 34 is brought into sliding contact with the inner circumferential surface of the insertion hole 33.
As shown in FIG. 3, this guide portion 34 has pins 35 for preventing rotation protruding from each other at 90° intervals at different angles of 45° in the circumferential direction from the arm portion 25b of the pressure contact portion 25. Each of the pins 35 abuts against the corners on both sides facing the insertion hole 33 of the upper grid plate 26, thereby preventing rotation of the instrumentation tube body 24, and preventing the pressure contact portion 25 from rotating.
This prevents the arm portion 25b from coming off the recess 32 of the upper lattice plate 26.

また、ガイド部34の上端には計装管本体24
吊り上げおよび吊り降し用の吊輪36を設けてい
る。
Further, an instrumentation tube main body 24 is provided at the upper end of the guide portion 34.
A hanging ring 36 for lifting and lowering is provided.

次に作用を説明する。 Next, the action will be explained.

原子炉の運転停止時における低温下では、圧接
部25のアーム部25bが形状記憶効果によつ
て、第5図に示すように上部格子板26の挿通孔
33よりも小径な状態まで収縮する。
At low temperatures when the reactor is shut down, the arm portion 25b of the press-contact portion 25 contracts to a smaller diameter than the insertion hole 33 of the upper grid plate 26 due to the shape memory effect, as shown in FIG.

そこで、炉内計装管23を炉心に装荷する場合
には、第6図Aに示すように、天井クレーン37
によつて吊輪36を吊り上げた状態とし、その炉
内計装管23を原子炉圧力容器21の上方から上
部格子板26の挿通孔33を介して吊り降す。そ
して、第6図Bに示すように、さらに吊り降して
計装管本体24の下端部をインコアハウジング2
8およびインコアフランジ29内に挿入する。最
大限吊り降すと、圧接部25のアーム部25bが
上部格子板26の窪み32に配置するとともに、
ガイド部34が挿通孔33内に摺接し第5図に示
す状態となる。そこで、天井クレーン37のフツ
ク37aを取り外せばよい。
Therefore, when loading the in-core instrumentation tube 23 into the reactor core, as shown in FIG. 6A, an overhead crane 37
The suspension ring 36 is suspended by the above, and the in-core instrumentation pipe 23 is suspended from above the reactor pressure vessel 21 through the insertion hole 33 of the upper grid plate 26. Then, as shown in FIG. 6B, the lower end of the instrumentation tube body 24 is further lowered into the in-core housing 2.
8 and into the in-core flange 29. When suspended to the maximum extent, the arm portion 25b of the pressure contact portion 25 is placed in the recess 32 of the upper lattice plate 26, and
The guide portion 34 slides into the insertion hole 33, resulting in the state shown in FIG. Therefore, the hook 37a of the overhead crane 37 can be removed.

前記の炉内計装管23の吊り降し操作は、同一
箇所で真直ぐに降すだけでよく、横方向の移動操
作は不必要である。したがつて、第10図A〜D
に示す従来例のように横方向の移動および治具に
よる炉内計装管の上端部の上部格子板への装着固
定等の複雑な操作は不要となり、従来のものに比
べて据付操作が簡便化となる。
The above-mentioned operation of lifting and lowering the in-furnace instrumentation tube 23 only requires lowering it straight at the same location, and there is no need to move it in the lateral direction. Therefore, Figures 10 A to D
There is no need for complicated operations such as horizontal movement and mounting and fixing of the upper end of the in-furnace instrumentation tube to the upper grid plate using jigs as in the conventional example shown in Figure 2, making the installation process simpler than the conventional example. It becomes.

なお、取り外す場合には、前記の装着手順と逆
の操作を行なえばよく、この場合にも従来の操作
に比べて取り外し作業が大幅に軽減される。
In addition, when removing it, it is sufficient to perform the operation in reverse to the above-mentioned mounting procedure, and in this case also, the removal work is significantly reduced compared to the conventional operation.

炉内計装管23の据付後、原子炉運転を開始す
ることにより、炉内が高温となつた場合には、圧
接部25のアーム部25bが形状記憶効果によつ
て拡張し、第1図およよび第2図に示すようにロ
ーラ25cを介して上部格子板26の窪み32に
圧接する。これにより、炉内計装管23は炉心2
2に確実に固定された状態となる。
After the installation of the in-core instrumentation tube 23, when the inside of the reactor becomes high temperature by starting the reactor operation, the arm part 25b of the pressure welding part 25 expands due to the shape memory effect, and as shown in FIG. Then, as shown in FIG. 2, it is pressed against the recess 32 of the upper grid plate 26 via the roller 25c. As a result, the in-core instrumentation tube 23 is connected to the core 2.
2 and is securely fixed.

しかも、このような取扱いの容易な炉内計装管
でありながらも、固定手段としての圧接部25の
構成が従来のものに比べて簡単であり、構成部品
も減少できる。
Moreover, even though the in-furnace instrumentation tube is easy to handle, the configuration of the pressure contact portion 25 as a fixing means is simpler than that of the conventional one, and the number of components can be reduced.

さらに、従来の構造と異なり、圧接部25のア
ーム部25bが形状記憶効果によつて、原子炉停
止時には確実に第5図に示すような収縮状態とな
るため、炉内計装管23が上部格子板26に固着
する等の事態は生じない。したがつて、炉内計装
管23の切断等の必要もなくなり、この意味でも
作業性の向上が図れ、被曝低減、安全性向上等に
も資するものとなる。
Furthermore, unlike the conventional structure, the arm part 25b of the pressure welding part 25 is reliably contracted as shown in FIG. A situation such as sticking to the grid plate 26 does not occur. Therefore, there is no need to cut the in-furnace instrumentation tube 23, and in this sense as well, work efficiency can be improved, and this also contributes to reducing radiation exposure and improving safety.

なお、前記実施例では計装管本体24の上端に
ガイド部34を設け、このガイド部34を上部格
子板26の挿通孔に挿通させ、吊輪36を介して
炉内計装管23の吊り上げおよび吊り下げのみで
着脱作用が行なえるようにしたが、これは最も望
ましい実施の態様であつて、本発明はこのような
ものに限らず、ガイド部34および吊輪36を省
略した構成にするとともに、従来と同様に窪みの
みを設けた上部格子板に対して側方から着脱する
ようにしてもよい。
In the embodiment described above, a guide part 34 is provided at the upper end of the instrumentation tube main body 24, and this guide part 34 is inserted into the insertion hole of the upper grid plate 26, and the in-furnace instrumentation tube 23 is lifted up through the suspension ring 36. Although the attachment and detachment can be performed only by hanging, this is the most desirable embodiment, and the present invention is not limited to this. In addition, it may be attached and detached from the side with respect to an upper lattice plate provided with only depressions, as in the conventional case.

また、圧接部25の構成について、必ずしも前
記実施例に示した形状のものに限らず、他の形状
として実施してもよい。要するに、圧接部は上部
格子板26等の炉心支持板部に当接支持できる構
造であればよい。
Further, the configuration of the pressure contact portion 25 is not necessarily limited to the shape shown in the above embodiment, but may be implemented in other shapes. In short, the pressure contact portion may have any structure as long as it can be supported in contact with the core support plate portion such as the upper grid plate 26.

〔発明の効果〕〔Effect of the invention〕

以上のように、本発明に係る炉内計装管によれ
ば、炉心支持板部に当接支持させるための圧接部
を形状記憶合金によつて構成したことにより、比
較的簡単な構成で、しかも部品数が少ない構成で
確実に炉心への装着が可能となり、固着等も防止
できるようになるという作用効果を奏する。
As described above, according to the in-core instrumentation tube according to the present invention, the press-contact portion for abutting and supporting the core support plate portion is made of a shape memory alloy, so that the in-core instrumentation tube has a relatively simple configuration. In addition, it is possible to reliably attach it to the reactor core with a configuration that has a small number of parts, and it also has the advantage of being able to prevent sticking and the like.

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

第1図は本発明に係る炉内計装管の一実施例を
示す全体構成図、第2図は第1図に示す炉内計装
管の圧接部の構成を拡大して示す図、第3図は第
2図の平面図、第4図は本発明の炉内計装管の挿
着するための上部格子板の全体平面図、第5図は
圧接部の収縮した状態を示す拡大図、第6図A,
Bは作用をを示す説明図、第7図は従来例を示す
全体構成図、第8図は従来の炉内計装管の上端部
構成を示す拡大図、第9図は同じく下端部を示す
拡大図、第10図A〜Dは従来の炉内計装管の着
脱作用を示す説明図である。 22…炉心、23…炉内計装管、24…計装管
本体、25…圧接部、26…上部格子板(炉心支
持板部)、32…窪み、33…挿通孔、34…ガ
イド部。
FIG. 1 is an overall configuration diagram showing an embodiment of the in-core instrumentation tube according to the present invention, FIG. 3 is a plan view of FIG. 2, FIG. 4 is an overall plan view of the upper grid plate for inserting the in-furnace instrumentation tube of the present invention, and FIG. 5 is an enlarged view showing the compressed state of the pressure welding part. , Figure 6A,
B is an explanatory diagram showing the action, FIG. 7 is an overall configuration diagram showing a conventional example, FIG. 8 is an enlarged view showing the upper end configuration of a conventional in-furnace instrumentation tube, and FIG. 9 is also showing the lower end. The enlarged views and FIGS. 10A to 10D are explanatory diagrams showing the operation of attaching and detaching the conventional in-furnace instrumentation tube. 22... Core, 23... In-core instrumentation tube, 24... Instrumentation tube main body, 25... Pressure contact part, 26... Upper grid plate (core support plate part), 32... Hollow, 33... Insertion hole, 34... Guide part.

Claims (1)

【特許請求の範囲】 1 中空長尺な計装管本体内に中性子検出器を収
納し、その計装管本体の一端に設けた圧接部を炉
心支持板部に当接させて原子炉内に装荷する炉内
計装管において、前記圧接部を形状記憶合金製と
し、原子炉運転時の高温下で拡張するとともに原
子炉停止時の低温下で収縮する形状記憶を付与し
たことを特徴とする炉内計装管。 2 計装管本体は、圧接部のさらに先端側に環状
のガイド部を備え、そのガイド部を炉心支持板部
に穿設した挿通孔の内周面に摺接させ、前記計装
管本体を前記挿通孔を介して炉心支持板部に抜差
可能に支持してなる特許請求の範囲第1項記載の
炉内計装管。
[Scope of Claims] 1. A neutron detector is housed in a hollow long instrumentation tube body, and a pressure welding part provided at one end of the instrumentation tube body is brought into contact with a core support plate part to be inserted into a nuclear reactor. In the in-core instrumentation tube to be loaded, the pressure-welded portion is made of a shape memory alloy, and is provided with shape memory that expands under high temperatures during reactor operation and contracts under low temperatures during reactor shutdown. In-furnace instrumentation tube. 2. The instrumentation tube main body is provided with an annular guide portion on the distal end side of the pressure welding portion, and the guide portion is brought into sliding contact with the inner circumferential surface of the insertion hole drilled in the core support plate portion, so that the instrumentation tube main body is The in-core instrumentation tube according to claim 1, which is supported in a core support plate portion through the insertion hole so as to be insertable and removable.
JP62229461A 1987-09-16 1987-09-16 Reactor instrumentation pipe Granted JPS6473297A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP62229461A JPS6473297A (en) 1987-09-16 1987-09-16 Reactor instrumentation pipe

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP62229461A JPS6473297A (en) 1987-09-16 1987-09-16 Reactor instrumentation pipe

Publications (2)

Publication Number Publication Date
JPS6473297A JPS6473297A (en) 1989-03-17
JPH0520719B2 true JPH0520719B2 (en) 1993-03-22

Family

ID=16892565

Family Applications (1)

Application Number Title Priority Date Filing Date
JP62229461A Granted JPS6473297A (en) 1987-09-16 1987-09-16 Reactor instrumentation pipe

Country Status (1)

Country Link
JP (1) JPS6473297A (en)

Families Citing this family (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
AU2001276930B8 (en) 2000-07-18 2005-11-03 Hunter Douglas Industries B.V. Tubular slat for coverings for architectural openings
US6662851B2 (en) 2000-12-22 2003-12-16 Hunter Douglas Inc. Ladder operated covering with fixed vanes for architectural openings
US6901988B2 (en) 2001-07-16 2005-06-07 Hunter Douglas Inc. Shutter-like covering and hardware for architectural opening
JP6767850B2 (en) * 2016-12-02 2020-10-14 三菱重工業株式会社 Reactor water level detector and reactor

Also Published As

Publication number Publication date
JPS6473297A (en) 1989-03-17

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