JPS61139792A - Core support structure of nuclear reactor - Google Patents

Core support structure of nuclear reactor

Info

Publication number
JPS61139792A
JPS61139792A JP59260855A JP26085584A JPS61139792A JP S61139792 A JPS61139792 A JP S61139792A JP 59260855 A JP59260855 A JP 59260855A JP 26085584 A JP26085584 A JP 26085584A JP S61139792 A JPS61139792 A JP S61139792A
Authority
JP
Japan
Prior art keywords
core support
shroud
support structure
reactor
fuel
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.)
Pending
Application number
JP59260855A
Other languages
Japanese (ja)
Inventor
輝雄 伊藤
雅弘 小林
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 JP59260855A priority Critical patent/JPS61139792A/en
Publication of JPS61139792A publication Critical patent/JPS61139792A/en
Pending 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

  • Housings And Mounting Of Transformers (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〕 本発明は原子炉の炉心内に装架された燃料の水平移動を
拘束する炉心支持構造物に関する。
DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a core support structure for restraining horizontal movement of fuel installed in the core of a nuclear reactor.

〔発明の技術的背景とその問題点〕[Technical background of the invention and its problems]

一般に、沸騰水型原子炉の炉心部は第5図に示すように
構成されている。すなわち、原子炉圧力容器1の内部に
は円筒状のシュラウド2が原子炉圧力容器1と同心にし
てシュラウドサポート1Aの上に着座され1Bの箇所で
溶接により固定されている。このシュラウド2の上には
シュラウドヘッド3が設置されている。さらに、シュラ
ウド2の内部の上部位置には多数の矩形孔を有する上部
格子板4、その下部位置には多数の円孔を有する炉心支
持板5が設置されている。この上部格子板4の矩形孔と
相対する炉心支持板5の円孔の位置毎にそれぞれ長尺な
燃料集合体が配列装架されて、炉心部が構成されており
、その燃料集合体が炉心構成燃料6とされている。また
、上部格子板4と炉心支持板5とは、上下、から燃料6
の水平方向の移動を拘束している。
Generally, the core of a boiling water reactor is constructed as shown in FIG. That is, inside the reactor pressure vessel 1, a cylindrical shroud 2 is seated on a shroud support 1A concentrically with the reactor pressure vessel 1 and fixed by welding at a location 1B. A shroud head 3 is installed on this shroud 2. Furthermore, an upper lattice plate 4 having a large number of rectangular holes is installed at an upper position inside the shroud 2, and a core support plate 5 having a large number of circular holes is installed at a lower position thereof. Long fuel assemblies are arranged and mounted at the positions of the rectangular holes of the upper grid plate 4 and the circular holes of the core support plate 5, respectively, to constitute the reactor core. It is said to be constituent fuel 6. In addition, the upper grid plate 4 and the core support plate 5 are arranged so that the fuel 6
The horizontal movement of is restricted.

このようにして形成された炉心支持構造物を組立てる場
合には、先ずシュラウド2を原子炉圧力容器1と同心に
設置し、1Bの箇所で溶接した後、上部格子板4と炉心
支持板5とを同様にして原子炉圧力容器1と同心に設置
する。この場合上部格子板4は多数のクサビ4Aにより
、また炉心支持板5は多数のスタッドボルト5Aにより
シュラウド2に固定される。
When assembling the core support structure formed in this way, first the shroud 2 is installed concentrically with the reactor pressure vessel 1, and after welding at the location 1B, the upper grid plate 4 and the core support plate 5 are welded together. is similarly installed concentrically with the reactor pressure vessel 1. In this case, the upper grid plate 4 is fixed to the shroud 2 by a large number of wedges 4A, and the core support plate 5 is fixed to the shroud 2 by a large number of stud bolts 5A.

ところが上部格子板4と炉心支持板6との設置には厳し
い据付精度が要求され、前記の多数のくさび4 A r
3よびスタッドボルト5Aを使用する為に長期間の据付
日程が必要である。
However, installation of the upper grid plate 4 and the core support plate 6 requires strict installation precision, and the above-mentioned large number of wedges 4A r
3 and stud bolts 5A require a long installation schedule.

また、水平方向の地震力が作用した場合、上部格子板4
はくざび4Aにより拘束されている為に水平方向には移
動が生じないが、炉心支持板5はスタッドボルト5Aと
炉心支持板6のスタッドボルト用穴との間隙だけ移動を
生じ、これにより燃料6の下部が移動し、傾斜が生じ図
示はしていないが燃料6の間に設置しである制御棒の挿
入が阻害されてしまうおそれがある。また、シュラウド
2は溶接により原子炉圧力容器1に固定されている為、
万一シュラウド2に不具合が生じた場合、その取外しや
交換が困難となり、また、原子炉圧力容器1の内部で補
修を行なうことも放射線被曝jが多い為に同じく困難と
なり、原子炉の運転が阻害されてしまうという不都合が
あった。
In addition, when a horizontal seismic force acts, the upper lattice plate 4
Although the core support plate 5 does not move in the horizontal direction because it is restrained by the wedges 4A, the core support plate 5 moves by the gap between the stud bolt 5A and the stud bolt hole of the core support plate 6, and as a result, the fuel There is a risk that the lower part of fuel 6 may move and tilt, which may obstruct insertion of a control rod installed between fuel 6 (not shown). In addition, since the shroud 2 is fixed to the reactor pressure vessel 1 by welding,
In the unlikely event that a malfunction occurs in the shroud 2, it will be difficult to remove or replace it, and it will also be difficult to repair the inside of the reactor pressure vessel 1 due to high radiation exposure, and the operation of the reactor will be interrupted. There was the inconvenience of being obstructed.

〔発明の目的〕[Purpose of the invention]

本発明はこれらの事情を考慮してなされたもので、製作
が容易で、原子炉圧力容器内への据付工程を短縮するこ
とができ、かつ、補修や交換も容易であり、原子炉の安
全性および稼働率を向上させることのできる原子炉の炉
心支持構造物を提供することを目的とする。
The present invention has been made in consideration of these circumstances, and is easy to manufacture, shortens the installation process in the reactor pressure vessel, and is easy to repair and replace, thereby improving the safety of the reactor. An object of the present invention is to provide a core support structure for a nuclear reactor that can improve performance and availability.

〔発明の概要〕[Summary of the invention]

原子炉の炉心支持構造物は、原子炉の炉心内に装架され
た燃料をその上部において水平方向移動を拘束して配列
支持する上部格子板と、前記燃料をその下部において水
平方向移動を拘束して配列支持する炉心支持板と、前記
燃料の外周を囲む筒状のシュラウドとを予め一体に形成
し、かつ原子炉圧力容器内のシュラウドサポート上に着
脱自在にして形成したことを特徴とする。
The core support structure of a nuclear reactor includes an upper lattice plate that arranges and supports the fuel installed in the core of the reactor while restraining horizontal movement at the upper part thereof, and restraining the horizontal movement of the fuel at the lower part thereof. The reactor core support plate arranged and supported by the reactor and the cylindrical shroud surrounding the outer periphery of the fuel are integrally formed in advance and are detachably attached to the shroud support in the reactor pressure vessel. .

(発明の実施例) 以下、本発明の実施例を第1図から第4図について説明
する。
(Embodiments of the Invention) Hereinafter, embodiments of the present invention will be described with reference to FIGS. 1 to 4.

第1図は本発明の一実施例を示し、図中符号7は本実施
例の一体型の炉心支持構造物を示している。この炉心支
持構造物は、第5図に示ず従来のシュラウド2の上部1
112aと中間部用2b、上部格子板4および炉心支持
板5とを一体にし製作した屯のである。また、従来のシ
ュラウド2の下部112cはシュラウドサポート1Aと
一体の構造物とされている。
FIG. 1 shows an embodiment of the present invention, and reference numeral 7 in the figure indicates an integrated core support structure of this embodiment. This core support structure is not shown in FIG.
112a, intermediate section 2b, upper grid plate 4 and core support plate 5 are integrated into one piece. Further, the lower part 112c of the conventional shroud 2 is an integral structure with the shroud support 1A.

この炉心支持構造物7は、予め工場等においてシュラウ
E2の上部胴2a、中間部胴2b、上部格子板4および
炉心支持板5を一体あるいは一体的に製造される。よっ
て、第5図に示す上部格子板4と炉心支持板5の固定部
品である各多数のくざび4Aやスタッドボルト5Aが不
要になり1、製作も極めて容易である。
This core support structure 7 is manufactured in advance in a factory or the like by integrally or integrally with the upper shell 2a, intermediate shell 2b, upper lattice plate 4, and core support plate 5 of the shrou E2. Therefore, the large number of wedges 4A and stud bolts 5A, which are fixing parts between the upper grid plate 4 and the core support plate 5 shown in FIG. 5, are no longer required1, and manufacturing is extremely easy.

そして、予め一体的〔製造された炉心支持構造物7を原
子炉圧力容器1のシュラウド2の下部胴を兼ねるシュラ
ウドサポート1A上に載置し、多数のスタッドボルト8
により緊締結合される。この場合炉心支持+lr造物7
とスタッドボルト8との間には、第2図に示す中空円筒
状のスペーサ9または第3図に示す二重の偏心中空円筒
状のスペーサ9Aと9Bとを組み合せて介在させて、炉
心支持構造物7とスタッドボルト8との間隙をなくして
いる。
Then, the core support structure 7 which has been integrally manufactured in advance is placed on the shroud support 1A which also serves as the lower body of the shroud 2 of the reactor pressure vessel 1, and a large number of stud bolts 8 are mounted.
are tightly connected. In this case, core support + lr structure 7
A hollow cylindrical spacer 9 shown in FIG. 2 or a combination of double eccentric hollow cylindrical spacers 9A and 9B shown in FIG. The gap between the object 7 and the stud bolt 8 is eliminated.

このように本実施例の炉心支持構造物7においては、原
子炉圧力容器1内への据付カー容易であり、しかも炉心
支持構造物7に水平方向の地震力が作用してもそれの移
動は拘束されることになり、同時に燃料6の移動も拘束
され、燃料6の間に設置されている制御棒の挿入が阻害
されることもなくなる。
In this way, the core support structure 7 of this embodiment can be easily installed into the reactor pressure vessel 1, and even if a horizontal seismic force acts on the core support structure 7, it will not move. At the same time, the movement of the fuel 6 is also restrained, and the insertion of the control rods installed between the fuels 6 is no longer inhibited.

また、炉心支持構造物の原子炉圧力容器への設置はボル
ト結合等の着脱自在な手段を用いている為溶接は不要に
なりその結果溶接変形が生じなく据付精度が向上する。
Furthermore, since the core support structure is installed in the reactor pressure vessel using removable means such as bolted connections, welding is not required, and as a result, welding deformation does not occur and installation accuracy is improved.

そして、炉心支持構造物の取外しが可能であるから、補
修または交換も容易になり、炉心位置における原子炉圧
ツノ容器の内壁の検査または補水も容易に行なうことが
できる。
Since the core support structure can be removed, repair or replacement becomes easy, and the inner wall of the reactor pressure vessel at the core location can be easily inspected or water refilled.

また、本発明の炉心支持構造物は水平方向の地震力が作
用しても移動しない構造の為燃料の移動が拘束され制御
棒の挿入を阻害することもなく、ひいては原子炉の安全
性および稼働率の向上を図ることができる。
Furthermore, since the reactor core support structure of the present invention has a structure that does not move even when horizontal seismic force is applied, the movement of fuel is restricted and the insertion of control rods is not obstructed, thereby improving the safety and operation of the reactor. It is possible to improve the ratio.

第4図に示す本発明の他の実施例の炉心支持構造物7A
は、第5図に示ずシュラウドヘッド3のリム11M3a
とシュラウド2゛の上部胴2aとを一体にし、第1図に
示す炉心支持構造物7の構造をより単純にしその製作も
容易にしたものである。
Core support structure 7A of another embodiment of the present invention shown in FIG.
is the rim 11M3a of the shroud head 3, which is not shown in FIG.
The upper shell 2a of the shroud 2' is integrated with the upper body 2a of the shroud 2', thereby simplifying the structure of the core support structure 7 shown in FIG. 1 and making it easier to manufacture.

〔発明の効果) このように本発明の原子炉の炉心支持構造物は、シュラ
ウド、炉心支持板および上部格子板を一体的に形成した
もので、その剛性がより強くなり強度上の裕度が増し、
上部格子板および炉心支持板の固定部品が総て不要にな
り、このため不具合の発生率が減り信頼性が向上する。
[Effects of the Invention] As described above, the reactor core support structure of the present invention has a shroud, a core support plate, and an upper lattice plate integrally formed, and has stronger rigidity and a greater margin in terms of strength. increase,
All the fixing parts of the upper grid plate and the core support plate are no longer required, which reduces the incidence of failure and improves reliability.

また、上部格子板と炉心支持板の据付工程は全部不要に
なり建設工程の短縮を図ることができる等の効果を奏す
る。
Further, the installation process of the upper grid plate and the core support plate is completely unnecessary, resulting in effects such as being able to shorten the construction process.

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

第1図から第3図は本発明の原子炉の炉心支持構造物の
一実施例を示し、第1図は原子炉の断面図、第2図およ
び第3図は炉心支持構造物と原子炉圧力容器との結合状
態を示す詳細断面図、第4図は本発明の他の実施例を示
す$1図同様の断面図、第5図は従来の原子炉の要部を
示す断面図である。 1・・・原子炉圧力容器、2・・・シュラウド、3・・
・シュラウドヘッド、4・・・上部格子板、5・・・炉
心支持板、6・・・燃料、7,7A・・・一体型の炉心
支持構造物、8・・・スタッドボルト、9.9A、9B
・・・スペーサ。 出願人代理人   波 多 野   久第1図 第2図   第3図 第4図 第5rI!J
1 to 3 show an embodiment of the core support structure of a nuclear reactor according to the present invention, FIG. 1 is a sectional view of the reactor, and FIGS. 2 and 3 show the core support structure and the reactor. 4 is a sectional view similar to the $1 figure showing another embodiment of the present invention; FIG. 5 is a sectional view showing the main parts of a conventional nuclear reactor. . 1...Reactor pressure vessel, 2...Shroud, 3...
・Shroud head, 4... Upper grid plate, 5... Core support plate, 6... Fuel, 7,7A... Integrated core support structure, 8... Stud bolt, 9.9A , 9B
···Spacer. Applicant's agent Hisashi Hatano Figure 1 Figure 2 Figure 3 Figure 4 Figure 5rI! J

Claims (1)

【特許請求の範囲】 1、原子炉の炉心内に装架された燃料をその上部におい
て水平方向移動を拘束して配列支持する上部格子板と、
前記燃料をその下部において水平方向移動を拘束して配
列支持する炉心支持板と、前記燃料の外周を囲む筒状の
シュラウドとを予め一体に形成し、かつ原子炉圧力容器
内のシュラウドサポート上に着脱自在に設置したことを
特徴とする原子炉の炉心支持構造物。 2、シュラウドサポートには、スペーサを外嵌させたス
タッドボルトにより水平方向移動を拘束して緊締固着さ
れることを特徴とする特許請求の範囲第1項記載の原子
炉の炉心支持構造物。
[Claims] 1. An upper lattice plate that arranges and supports fuel installed in the core of a nuclear reactor while restricting horizontal movement at the upper part thereof;
A core support plate that arranges and supports the fuel while restraining horizontal movement at its lower part, and a cylindrical shroud surrounding the outer periphery of the fuel are integrally formed in advance, and are mounted on the shroud support in the reactor pressure vessel. A nuclear reactor core support structure characterized by being installed in a detachable manner. 2. The core support structure for a nuclear reactor as set forth in claim 1, wherein the shroud support is tightened and fixed to the shroud support by stud bolts having spacers fitted thereon to restrain horizontal movement.
JP59260855A 1984-12-12 1984-12-12 Core support structure of nuclear reactor Pending JPS61139792A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP59260855A JPS61139792A (en) 1984-12-12 1984-12-12 Core support structure of nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP59260855A JPS61139792A (en) 1984-12-12 1984-12-12 Core support structure of nuclear reactor

Publications (1)

Publication Number Publication Date
JPS61139792A true JPS61139792A (en) 1986-06-27

Family

ID=17353683

Family Applications (1)

Application Number Title Priority Date Filing Date
JP59260855A Pending JPS61139792A (en) 1984-12-12 1984-12-12 Core support structure of nuclear reactor

Country Status (1)

Country Link
JP (1) JPS61139792A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0418892U (en) * 1990-06-04 1992-02-17

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0418892U (en) * 1990-06-04 1992-02-17

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