JPH0652312B2 - Liquid metal cooled reactor - Google Patents

Liquid metal cooled reactor

Info

Publication number
JPH0652312B2
JPH0652312B2 JP60192004A JP19200485A JPH0652312B2 JP H0652312 B2 JPH0652312 B2 JP H0652312B2 JP 60192004 A JP60192004 A JP 60192004A JP 19200485 A JP19200485 A JP 19200485A JP H0652312 B2 JPH0652312 B2 JP H0652312B2
Authority
JP
Japan
Prior art keywords
reactor
liquid metal
metal cooled
support structure
guide tube
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
JP60192004A
Other languages
Japanese (ja)
Other versions
JPS6252491A (en
Inventor
和浩 松崎
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 JP60192004A priority Critical patent/JPH0652312B2/en
Publication of JPS6252491A publication Critical patent/JPS6252491A/en
Publication of JPH0652312B2 publication Critical patent/JPH0652312B2/en
Anticipated expiration legal-status Critical
Expired - Lifetime 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)
  • Physical Or Chemical Processes And Apparatus (AREA)

Description

【発明の詳細な説明】 〔発明の技術分野〕 本発明は液体金属冷却型原子炉において、遮蔽プラグ4
を貫通して設置される原子炉内挿入機器案内管の耐震性
を向上させると共に、炉内カバーガスの上昇を防止でき
るようにした原子炉内挿入機器案内管を備えた原子炉に
関する。
Description: TECHNICAL FIELD OF THE INVENTION The present invention relates to a shield plug 4 in a liquid metal cooled nuclear reactor.
The present invention relates to a reactor equipped with a guide tube for inserting a device inside the reactor, which is capable of improving the seismic resistance of the guide pipe for the inserting device inside the reactor and preventing the rise of cover gas in the reactor.

[発明の技術的背景とその問題点] 一般に、ナトリウムなどの液体金属を冷却材とする液体
金属冷却型原子炉は第2図に例示するように、炉心部1
を収納する原子炉容器2の上端を炉心上部機構3を搭載
した遮蔽プラグ4によって閉塞されている。
[Technical Background of the Invention and Problems Thereof] In general, a liquid metal cooled nuclear reactor using a liquid metal such as sodium as a coolant has a core portion 1 as shown in FIG.
The upper end of the reactor vessel 2 accommodating the above is closed by a shield plug 4 on which the reactor core upper mechanism 3 is mounted.

この遮蔽プラグ4には炉心上部機構3と炉心部1上面の
間隙部の異常の有無を測定するナトリウム透視装置や、
新燃料または使用済燃料を原子炉容器2内へ出し入れす
る炉内中継装置などの原子炉内挿入機器5を挿入するた
めの開口部が藻けられている。
The shielding plug 4 has a sodium see-through device for measuring the presence or absence of an abnormality in the gap between the upper core mechanism 3 and the upper surface of the core 1,
An opening for inserting an in-reactor insertion device 5 such as an in-reactor relay device for inserting and removing new fuel or spent fuel into and out of the reactor vessel 2 is provided.

上述のナトリウム透視装置や炉内中継装置などの原子炉
内挿入機器5は円筒状の細長い機器であり、地震時など
に原子炉内挿入機器5が原子炉容器2内に設置された原
子炉容器内筒6に衝突することを防止すると共に、原子
炉内挿入機器5の挿入時に遮蔽プラグ4の熱遮蔽板7な
どとの干渉を防いで挿入性を向上させるために、上述の
開口部には原子炉内挿入機器案内管8が設置されてい
る。この原子炉内挿入機器案内管の上端にはドアバルブ
9が藻けられている。なお第2図中、符号10は遮蔽プ
ラグ冷却層を示す。
The reactor insertion device 5 such as the above-mentioned sodium see-through device and in-reactor relay device is a cylindrical elongated device, and the reactor insertion device 5 is installed in the reactor vessel 2 during an earthquake or the like. In order to prevent the collision with the inner cylinder 6 and prevent the interference with the heat shield plate 7 of the shield plug 4 at the time of inserting the reactor insertion device 5, the above-mentioned opening is provided in order to improve the insertability. An in-reactor insertion device guide tube 8 is installed. A door valve 9 is provided on the upper end of the device guide tube for inserting equipment in the nuclear reactor. In FIG. 2, reference numeral 10 indicates a shielding plug cooling layer.

原子炉内挿入機器案内管8は、第3図に示すようにフラ
ンジ部8aを介して遮蔽プラグ4とドアバルブ9の間に
機密に固着されており、また、原子炉内挿入機器案内管
8の下端には、原子炉内挿入機器5の途中に係合する挿
入機器支持部8bが突設されている。
As shown in FIG. 3, the in-reactor insertion device guide pipe 8 is securely fixed between the shield plug 4 and the door valve 9 via the flange portion 8a, and the in-reactor insertion device guide pipe 8 is At the lower end, an insertion device supporting portion 8b that engages in the middle of the insertion device 5 in the nuclear reactor is projected.

上述のように構成した従来の液体金属冷却型原子炉にお
いては、遮蔽プラグ4の開口部と原子炉内挿入機器案内
管8の間にアニュラス部12が存在しており、炉内カバ
ーガス空間11の高放射能のFPガスが自然対流により
アニュラス部12内を上昇してくる。
In the conventional liquid metal cooled nuclear reactor configured as described above, the annulus portion 12 exists between the opening of the shield plug 4 and the reactor insertion device guide tube 8, and the reactor cover gas space 11 FP gas having high radioactivity rises in the annulus portion 12 due to natural convection.

このFPガスは案内管8のフランジ部8aと遮蔽プラグ
4の間に介挿したOリングによってシールされ、炉外へ
の漏出を阻止される。
This FP gas is sealed by an O-ring inserted between the flange portion 8a of the guide tube 8 and the shield plug 4, and is prevented from leaking out of the furnace.

しかしながら、FPガスは高い放射能を帯びているた
め、これがアニュラス部12を通してフランジ部8a下
部まで上昇する構造の原子炉においては、遮蔽プラグ4
上面の放射線量を許容値以下に押えるため、遮蔽プラグ
4上面に大量の放射線遮蔽体13を設置する必要があっ
た。
However, since the FP gas has high radioactivity, in the reactor having a structure in which this rises through the annulus portion 12 to the lower portion of the flange portion 8a, the shield plug 4
In order to keep the radiation dose on the upper surface below the allowable value, it is necessary to install a large amount of radiation shields 13 on the upper surface of the shield plug 4.

また、原子炉内挿入機器案内管8は上端のフランジ部8
aによって遮蔽プラグ4に固定されているのみであるた
め、長い片持ち梁状の支持構造となり、原子炉内挿入機
器5を挿入機器支持部8bで耐震支持するのに必要な剛
性を確保するためには、大径で厚肉の構造とせざるを得
ないという欠点があった。
In addition, the reactor insertion device guide tube 8 has a flange portion 8 at the upper end.
Since it is only fixed to the shielding plug 4 by a, it has a long cantilever-like support structure, and in order to secure the rigidity necessary to support the in-reactor insertion device 5 with the insertion device support portion 8b for earthquake resistance. Had a drawback that it had a large diameter and a thick structure.

〔発明の目的〕[Object of the Invention]

本発明は背景技術における上述のごとき欠点を除去すべ
くなされたもので、原子炉内挿入機器5を高い剛性で耐
震支持すると共に炉内カバーガスが遮蔽プラグ4上部へ
上昇してくるのを防止する機能を有する原子炉内挿入機
器案内管8を備えた液体金属冷却型原子炉を提供するこ
とを目的とする。
The present invention has been made to eliminate the above-mentioned drawbacks of the background art, and supports seismic support of the reactor insertion device 5 with high rigidity and prevents the reactor cover gas from rising above the shielding plug 4. It is an object of the present invention to provide a liquid metal cooling type nuclear reactor equipped with a guide tube 8 for inserting equipment in a nuclear reactor having the function of

〔発明の概要〕[Outline of Invention]

本発明の液体金属冷却型原子炉は、遮蔽プラグを貫通す
る原子炉内挿入機器を案内する案内管が円筒軸シール構
造部とテーパー支持構造部の2点で前記遮蔽プラグの開
口部内に支持されていることを特徴とするものである。
In the liquid metal cooled nuclear reactor of the present invention, a guide tube for guiding the equipment inserted into the reactor, which penetrates the shield plug, is supported in the opening of the shield plug at two points of the cylindrical shaft seal structure portion and the taper support structure portion. It is characterized by that.

〔発明の実施例〕Example of Invention

以下、図面を参照して本発明の実施例を説明する。 Embodiments of the present invention will be described below with reference to the drawings.

第1図は本発明の原子炉の特徴部分を示すもので、第2
図または第3図におけると同一部分には同一の符号を付
し、詳細な説明は省略する。
FIG. 1 shows the characteristic part of the nuclear reactor of the present invention.
The same parts as those in FIG. 3 or FIG. 3 are designated by the same reference numerals, and detailed description thereof will be omitted.

本発明において、遮蔽プラグ4の開口部内に装着された
原子炉内挿入機器案内管20は第1図に示すように遮蔽
プラグ4の開口部の内径とほぼ同径の外径とされ、Oリ
ング21によって遮蔽プラグ4の開口部との間をシール
とされる円筒軸シール構造部20aと、この円筒軸シー
ル構造部20aと挿入機器支持部20bとの中間位置に
おいて、遮蔽プラグ4側に形成してテーパー孔4aに気
密に係合するテーパー支持構造部20cとから構成され
ている。また、ドアバルブ9はOリング22を介して遮
蔽プラグ4上に直接取付けられている。
In the present invention, the reactor insertion device guide tube 20 installed in the opening of the shielding plug 4 has an outer diameter substantially the same as the inner diameter of the opening of the shielding plug 4 as shown in FIG. It is formed on the shield plug 4 side at an intermediate position between the cylindrical shaft seal structure portion 20a and the insertion device supporting portion 20b, which is a seal between the cylindrical shaft seal structure portion 20a and the opening of the shield plug 4 by 21. And a taper support structure portion 20c which is hermetically engaged with the taper hole 4a. Further, the door valve 9 is directly mounted on the shield plug 4 via the O-ring 22.

上述のよう構成した本発明の液体金属冷却型原子炉にお
いては、炉内カバーガス空間11に連通するアニュラス
部12はテーパー支持構造部20cによって途中を閉塞
されているので、炉内カバーガスがそれよりも上方へ流
入することはない。従って、炉内カバーガスが高い放射
能を帯びていても遮蔽プラグ4上面の放射線量はさほど
高くはなく、第3図につき説明した遮蔽体13などは不
要となる。
In the liquid metal cooled reactor of the present invention configured as described above, the annulus portion 12 communicating with the in-reactor cover gas space 11 is partially closed by the tapered support structure portion 20c, so that the in-reactor cover gas is It does not flow upwards. Therefore, even if the furnace cover gas has high radioactivity, the radiation dose on the upper surface of the shield plug 4 is not so high, and the shield 13 described with reference to FIG.

また、原子炉内挿入機器案内管20は円筒軸シール構造
部20aとテーパー支持構造部20cの2点によって遮
蔽プラグ4に支持されるので、従来の片持ち梁支持構造
の案内管8に比較して耐震剛性が大幅に向上しており、
従って、その肉厚を薄くすることも可能である。
Further, the in-reactor insertion device guide tube 20 is supported by the shield plug 4 by the two points of the cylindrical shaft seal structure portion 20a and the taper support structure portion 20c, so that the guide tube 8 of the conventional cantilever support structure is compared with the guide tube 8. Seismic resistance has been significantly improved,
Therefore, it is possible to reduce the wall thickness.

なお、前述の円筒軸シール構造部20aのOリング21
はドアバルブ9の取外し補修時に炉内の気密性を保つた
め使用されるものである。
The O-ring 21 of the cylindrical shaft seal structure portion 20a described above is used.
Is used to maintain airtightness in the furnace when removing and repairing the door valve 9.

〔発明の効果〕〔The invention's effect〕

以上の説明から明らかなように、本発明の液体金属冷却
型原子炉においては、原子炉内挿入機器案内管が円筒軸
シール構造部とテーパー支持構造部の2点支持構造であ
り、しかもそれらの支持スパンの間隔を大きくとること
ができるので、案内管の耐震性が向上し、小径・薄肉構
造にすることができる。
As is clear from the above description, in the liquid metal cooled nuclear reactor of the present invention, the reactor insertion device guide tube has the two-point support structure of the cylindrical shaft seal structure part and the taper support structure part, and Since the spacing between the supporting spans can be made large, the earthquake resistance of the guide tube is improved, and a small diameter and thin wall structure can be achieved.

また、遮蔽プラグの上面から離間した位置にあるテーパ
ー支持構造部において面接触部が形成され、この部分で
アニュラス部内を自然対流する炉内カバーガスの上昇を
阻止することができるので、遮蔽プラグ上面の放射線量
は低い値に保たれ、従来のように大量の放射線遮蔽体を
使用する必要はなくなる。
In addition, since a surface contact portion is formed in the tapered support structure portion located at a position separated from the upper surface of the shield plug, the rise of the cover gas in the furnace that naturally convects in the annulus portion can be prevented at this portion. The radiation dose is kept low, eliminating the need to use large amounts of radiation shields as in the past.

しかも、原子炉内挿入機器案内管は原子炉カバーガスな
どのバゥンダリングに直接係わるものでないため、設計
や品質保証上、高品位を要求されることはない。従って
本発明によれば、液体冷却型原子炉の信頼性を高めるこ
とができ、同時にかなりのコストダウンも可能である。
Moreover, since the guide pipe for inserting equipment inside the nuclear reactor is not directly related to the boundarying of the reactor cover gas and the like, high quality is not required for design and quality assurance. Therefore, according to the present invention, the reliability of the liquid-cooled reactor can be improved, and at the same time, the cost can be considerably reduced.

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

第1図は本発明の原子炉の要部を示すもので、原子炉内
挿入機器案内管近傍の縦断面図、第2図は液体金属冷却
型原子炉の概略構成を示す縦断面図、第3図は従来の原
子炉内挿入機器案内管を説明する縦断面図である。 1……炉心部 2……容器 3……炉心上部機構 4……遮蔽プラグ 5……原子炉内挿入機器 6……原子炉容器内筒 7……熱遮蔽板 8……原子炉内挿入機器案内管 9……ドアバルブ 10……冷却器 11……炉内カバーガス空間 12……アニュラス部 13……遮蔽体 20……原子炉内挿入機器案内管 20a……円筒軸シール構造部 20b……挿入機器支持部 20c……テーパー支持構造部
FIG. 1 shows a main part of a nuclear reactor of the present invention. FIG. 1 is a vertical cross-sectional view in the vicinity of a guide tube for inserting equipment in the reactor, and FIG. 2 is a vertical cross-sectional view showing a schematic configuration of a liquid metal cooled nuclear reactor. FIG. 3 is a vertical cross-sectional view illustrating a conventional guide pipe for inserting equipment in a nuclear reactor. 1 ... Core part 2 ... Vessel 3 ... Core upper part mechanism 4 ... Shielding plug 5 ... Reactor insertion device 6 ... Reactor container inner cylinder 7 ... Heat shield plate 8 ... Reactor insertion device Guide tube 9 ...... Door valve 10 ...... Cooler 11 ...... Reactor cover gas space 12 ...... Annulus part 13 ...... Shield 20 ...... Reactor insertion equipment guide tube 20a ...... Cylindrical shaft seal structure part 20b ...... Insertion device support 20c ... Taper support structure

Claims (2)

【特許請求の範囲】[Claims] 【請求項1】液体金属冷却型原子炉の遮蔽プラグを貫通
する原子炉内挿入機器を案内する案内管が円筒軸シール
構造部とテーパー支持構造部の2点で前記遮蔽プラグの
開口部内に支持されていることを特徴とする液体金属冷
却型原子炉。
1. A guide tube for penetrating a shield plug of a liquid metal cooled nuclear reactor for guiding equipment inserted into the reactor is supported in the opening of the shield plug at two points of a cylindrical shaft seal structure and a taper support structure. Liquid metal cooled nuclear reactor characterized by being
【請求項2】遮蔽プラグと原子炉内挿入機器案内管の間
に形成されたアニュラス部が遮蔽プラグの上面より離間
した位置において、テーパー支持構造部により閉塞さ
れ、炉内カバーガスがテーパー支持構造部を越えて上昇
することを阻止されていることを特徴とする特許請求の
範囲第1項記載の液体金属冷却型原子炉。
2. The taper support structure closes the annulus portion formed between the shield plug and the reactor insertion instrument guide tube at a position separated from the upper surface of the shield plug by the taper support structure portion, and the reactor cover gas has a taper support structure. The liquid metal cooled nuclear reactor according to claim 1, wherein the liquid metal cooled nuclear reactor is prevented from rising beyond a portion.
JP60192004A 1985-09-02 1985-09-02 Liquid metal cooled reactor Expired - Lifetime JPH0652312B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP60192004A JPH0652312B2 (en) 1985-09-02 1985-09-02 Liquid metal cooled reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP60192004A JPH0652312B2 (en) 1985-09-02 1985-09-02 Liquid metal cooled reactor

Publications (2)

Publication Number Publication Date
JPS6252491A JPS6252491A (en) 1987-03-07
JPH0652312B2 true JPH0652312B2 (en) 1994-07-06

Family

ID=16284000

Family Applications (1)

Application Number Title Priority Date Filing Date
JP60192004A Expired - Lifetime JPH0652312B2 (en) 1985-09-02 1985-09-02 Liquid metal cooled reactor

Country Status (1)

Country Link
JP (1) JPH0652312B2 (en)

Also Published As

Publication number Publication date
JPS6252491A (en) 1987-03-07

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