JPS6339675Y2 - - Google Patents

Info

Publication number
JPS6339675Y2
JPS6339675Y2 JP1981067119U JP6711981U JPS6339675Y2 JP S6339675 Y2 JPS6339675 Y2 JP S6339675Y2 JP 1981067119 U JP1981067119 U JP 1981067119U JP 6711981 U JP6711981 U JP 6711981U JP S6339675 Y2 JPS6339675 Y2 JP S6339675Y2
Authority
JP
Japan
Prior art keywords
reactor vessel
guide tube
reactor
branch
neutron flux
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
Application number
JP1981067119U
Other languages
Japanese (ja)
Other versions
JPS57179198U (en
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 filed Critical
Priority to JP1981067119U priority Critical patent/JPS6339675Y2/ja
Publication of JPS57179198U publication Critical patent/JPS57179198U/ja
Application granted granted Critical
Publication of JPS6339675Y2 publication Critical patent/JPS6339675Y2/ja
Expired 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

【考案の詳細な説明】 この考案は、中性子検出管案内管を改良した原
子炉炉内中性子束計測装置に関する。
[Detailed Description of the Invention] This invention relates to an in-reactor neutron flux measuring device with an improved neutron detection tube guide tube.

第1図のこの種の装置として、特開昭55−6222
で知られている第1図に示すものがある。この第
1図において、1は原子炉容器、2は原子炉容器
1を貫通している原子炉容器内外に延びる中性子
検出器の案内管である。
As this type of device shown in Fig. 1, there is a
There is one known as shown in Figure 1. In FIG. 1, 1 is a reactor vessel, and 2 is a guide tube for a neutron detector that penetrates the reactor vessel 1 and extends inside and outside the reactor vessel.

案内管2の原子炉容器1内の一端は気密封止さ
れており、原子炉容器1の外側の他端は中性子検
出器を挿入するために開放されている。
One end of the guide tube 2 inside the reactor vessel 1 is hermetically sealed, and the other end outside the reactor vessel 1 is open for insertion of a neutron detector.

また、案内管2のまわりに、この案内管2に沿
つて加熱保温装置3が設けられており、案内管2
を高温に保つためのものである。
Further, a heating and heat-retaining device 3 is provided around the guide tube 2 along the guide tube 2.
This is to keep the temperature at a high temperature.

一般に、案内管2の酸化防止のため、案内管内
に炭酸ガスが注入されるが、この炭酸ガスと空
気、水素が炉容器内にある案内管内で反応し、高
温では気体であるが、低温では固化する異物が生
成される。この異物が案内管内壁に固着すると、
中性子検出器の炉容器内への挿入引き抜きが困難
となる。
Generally, carbon dioxide gas is injected into the guide tube to prevent oxidation of the guide tube 2, but this carbon dioxide gas, air, and hydrogen react in the guide tube inside the furnace vessel, and it becomes a gas at high temperatures, but at low temperatures. Foreign matter is produced that hardens. If this foreign material sticks to the inner wall of the guide tube,
It becomes difficult to insert and withdraw the neutron detector into the reactor vessel.

加熱保温装置3はこの異物が原子炉容器1外に
ある低温部案内管内壁に付着するのを防止するた
めのものであるが、このためには、原子炉容器1
外にある案内管2を全長に亘つて加熱しなければ
ならず、加熱装置が長大になるほか、開放端から
出てきた異物は付近の機器に付着し、悪影響を及
ぼすおそれがあるなどの欠点があつた。
The heating and insulation device 3 is intended to prevent this foreign material from adhering to the inner wall of the low-temperature section guide tube outside the reactor vessel 1;
Disadvantages include the need to heat the entire length of the guide tube 2 located outside, which makes the heating device long, and foreign matter that comes out of the open end may adhere to nearby equipment and have an adverse effect. It was hot.

この考案は、上記従来の欠点を除去するために
なされたもので、原子炉容器外にある案内管の途
中に枝管を設け、この枝管を冷却することによ
り、案内管の加熱装置を短くすることができ、し
かも確実に異物をトラツプすることのできる原子
炉炉内中性子束計測装置を提供することを目的と
する。
This idea was made in order to eliminate the above-mentioned drawbacks of the conventional method. By providing a branch pipe in the middle of the guide pipe outside the reactor vessel and cooling this branch pipe, the heating device of the guide pipe can be shortened. It is an object of the present invention to provide a neutron flux measurement device in a nuclear reactor that can trap foreign matter reliably.

以下、この考案の原子炉炉内中性子束計測装置
の実施例について図面に基づき説明する。第2図
はその一実施例における案内管部分の断面図であ
る。この第2図において、第1図と同一部分には
同一符号を付してその説明を省略し、第1図とは
異なる部分を重点的に述べることにする。
Hereinafter, an embodiment of the in-reactor neutron flux measuring device of this invention will be described based on the drawings. FIG. 2 is a sectional view of a guide tube portion in one embodiment. In FIG. 2, parts that are the same as those in FIG. 1 are given the same reference numerals, and their explanation will be omitted, and the parts that are different from those in FIG. 1 will be mainly described.

第2図において、原子炉容器1、加熱保護装置
3は第1図と同様であり、また、案内管2におい
ても、原子炉容器1の一端は気密封止されている
のも第1図と同様である。しかしながら以下に述
べる点が第1図とは異なるものである。
In FIG. 2, the reactor vessel 1 and thermal protection device 3 are the same as in FIG. 1, and also in the guide tube 2, one end of the reactor vessel 1 is hermetically sealed as in FIG. The same is true. However, it differs from FIG. 1 in the following points.

すなわち、原子炉容器1の外側にある案内管2
の途中に枝管4が設けられており、この枝管4は
冷却装置5により冷却されるようになつている。
そして、枝管4を設けた位置と原子炉容器1を案
内管2で貫通する部との間の案内管2には、加熱
保温装置3が従来と同様にして設けられている。
That is, the guide tube 2 outside the reactor vessel 1
A branch pipe 4 is provided in the middle, and this branch pipe 4 is cooled by a cooling device 5.
A heating and heat-retaining device 3 is provided in the guide tube 2 between the position where the branch pipe 4 is provided and the portion where the guide tube 2 penetrates the reactor vessel 1 in the same manner as in the prior art.

このように構成されているので、原子炉容器1
内にある案内管2の内部に生じた異物は加熱保温
装置3が施されている案内管部分では固着せず、
枝管4の冷却部に触れたとき固着するので、異物
がさらに案内管2の開放端に向かつて移動して行
くことはなく、確実に枝管内部に沈着させること
ができる。
With this configuration, reactor vessel 1
Foreign matter generated inside the guide tube 2 will not stick to the guide tube section where the heating and heat retention device 3 is installed.
Since the foreign matter is fixed when it touches the cooling part of the branch pipe 4, the foreign matter does not move further toward the open end of the guide pipe 2, and can be reliably deposited inside the branch pipe.

なお、枝管4の内部に金属小片を多数入れてお
けば、異物の沈着効果が一層よくなる。
Note that if a large number of small metal pieces are placed inside the branch pipe 4, the effect of depositing foreign matter will be further improved.

また、上記実施例では、加熱保温装置3は枝管
4の位置と原子炉容器1の貫通部分との間の案内
管2にのみ施した場合を例示したが、この加熱保
温装置3または保温装置をさらに開放端の方向に
少し延長することもできる。
Furthermore, in the above embodiment, the heating and heat-insulating device 3 is applied only to the guide pipe 2 between the position of the branch pipe 4 and the penetrating portion of the reactor vessel 1. can also be extended a little further toward the open end.

さらに、多数本の案内管を有する原子炉内中性
子束計測装置においては、それぞれの案内管2に
設けられた枝管を複数本同一の冷却装置で冷却す
ることもできる。
Furthermore, in an in-reactor neutron flux measuring device having a large number of guide tubes, a plurality of branch tubes provided in each guide tube 2 can be cooled by the same cooling device.

さらに、異物の固化温度は45〜50℃であるか
ら、周囲の温度によつては、枝管の冷却は自然放
冷によつてもよい。
Further, since the solidification temperature of foreign matter is 45 to 50°C, depending on the ambient temperature, cooling of the branch pipes may be performed by natural cooling.

以上のように、この考案の原子炉炉内中性子束
計測装置によれば、原子炉容器の外側にある案内
管の途中に枝管を設け、この枝管を冷却するよう
にしたので、案内管の加熱長さを短くでき、しか
も、原子炉容器内にある案内管内部で発生した異
物を確実に枝管に沈着させることができ、中性子
検出器の挿入、引き出しが円滑に行える効果があ
る。
As described above, according to the in-reactor neutron flux measuring device of this invention, a branch pipe is provided in the middle of the guide pipe outside the reactor vessel, and this branch pipe is cooled. This has the effect of shortening the heating length of the reactor, and also ensuring that foreign matter generated inside the guide tube inside the reactor vessel is deposited in the branch pipe, allowing smooth insertion and withdrawal of the neutron detector.

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

第1図は従来の原子炉炉内中性子束計測装置の
案内管部分の断面図、第2図はこの考案の原子炉
炉内中性子束計測装置の一実施例における案内管
部分の断面図である。 1……原子炉容器、2……中性子検出器の案内
管、3……加熱保温装置、4……枝管、5……冷
却装置。なお、図中同一符号は同一部分または相
当部分を示す。
FIG. 1 is a cross-sectional view of a guide tube portion of a conventional in-reactor neutron flux measuring device, and FIG. 2 is a cross-sectional view of a guide tube portion in an embodiment of the in-core neutron flux measuring device of this invention. . 1... Nuclear reactor vessel, 2... Guide tube for neutron detector, 3... Heating and heat retention device, 4... Branch pipe, 5... Cooling device. Note that the same reference numerals in the figures indicate the same or equivalent parts.

Claims (1)

【実用新案登録請求の範囲】 (1) 原子炉容器、一端がこの原子炉容器の壁を貫
通して原子炉容器内において気密封止され他端
が原子炉容器の外部で開放されかつこの外部の
所定個所に枝管を有する中性子検出管の案内
管、上記枝管を冷却する冷却装置、案内管を高
温に保つ保温装置または加熱保温装置を備えて
なる原子炉炉内中性子束計測装置。 (2) 案内管は複数本設けられそれぞれ多数の枝管
を有するとともに複数の枝管を同一の冷却装置
で冷却することを特徴とする実用新案登録請求
の範囲第1項記載の原子炉炉内中性子束計測装
置。 (3) 枝管は内部に多数の金属小片を多数入れるこ
とを特徴とする実用新案登録請求の範囲第1項
記載または第2項記載の原子炉炉内中性子束計
測装置。
[Scope of Claim for Utility Model Registration] (1) A reactor vessel, one end of which penetrates the wall of the reactor vessel and is hermetically sealed within the reactor vessel, and the other end is open outside the reactor vessel, and An in-reactor neutron flux measuring device comprising a guide tube for a neutron detection tube having branch tubes at predetermined locations, a cooling device for cooling the branch tube, and a heat insulating device or heating heat insulating device to keep the guide tube at a high temperature. (2) A nuclear reactor interior according to claim 1 of the utility model registration claim, characterized in that a plurality of guide pipes are provided, each having a large number of branch pipes, and the plurality of branch pipes are cooled by the same cooling device. Neutron flux measurement device. (3) The in-reactor neutron flux measuring device according to claim 1 or 2, wherein the branch pipe has a large number of metal pieces inserted therein.
JP1981067119U 1981-05-09 1981-05-09 Expired JPS6339675Y2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1981067119U JPS6339675Y2 (en) 1981-05-09 1981-05-09

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1981067119U JPS6339675Y2 (en) 1981-05-09 1981-05-09

Publications (2)

Publication Number Publication Date
JPS57179198U JPS57179198U (en) 1982-11-13
JPS6339675Y2 true JPS6339675Y2 (en) 1988-10-18

Family

ID=29863134

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1981067119U Expired JPS6339675Y2 (en) 1981-05-09 1981-05-09

Country Status (1)

Country Link
JP (1) JPS6339675Y2 (en)

Also Published As

Publication number Publication date
JPS57179198U (en) 1982-11-13

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