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JPH01307694A - Overhead core spray - Google Patents

Overhead core spray

Info

Publication number
JPH01307694A
JPH01307694A JP63138425A JP13842588A JPH01307694A JP H01307694 A JPH01307694 A JP H01307694A JP 63138425 A JP63138425 A JP 63138425A JP 13842588 A JP13842588 A JP 13842588A JP H01307694 A JPH01307694 A JP H01307694A
Authority
JP
Japan
Prior art keywords
core
ring
overhead
shroud
core spray
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
JP63138425A
Other languages
Japanese (ja)
Inventor
Hideaki Takahashi
秀明 高橋
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 JP63138425A priority Critical patent/JPH01307694A/en
Publication of JPH01307694A publication Critical patent/JPH01307694A/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

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

PURPOSE:To suppress damages at the time of welding by providing plural pieces of supporting plates which are distributed in the circumferential direction of a support ring and have large rigidity in the axial direction of a core to the inner peripheral face of the supporting ring and fixing and supporting said ring to the front ends of these supporting plates. CONSTITUTION:The overhead core spray 6 is mounted to the support ring 7 via plural pieces of the support plates 8 disposed radially to the inside peripheral face of the ring 7. The respective support plates 8 are increased in height, i.e., in the size in the axial direction of the reactor pressure vessel, namely, the core thereof to have the large rigidity in said direction. The support plates are, therefore, capable of reacting sufficiently with any of the vertical component and lateral and twist direction components of the vibration force at the time of steam passage. The damages of respective weld zones are thus suppressed as far as possible.

Description

【発明の詳細な説明】 [発明の目的] (産業上の利用分野) 本発明は沸騰水型原子炉の原子炉圧力容器内に取り付け
られるオーバヘッドコアスプレィに係る。
DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial Application Field) The present invention relates to an overhead core spray installed in a reactor pressure vessel of a boiling water nuclear reactor.

(従来の技術) 第4図、第5図は従来のオーバヘッドコアスプレィの平
面図、縦断面図である。これ等の各図において、1は原
子炉圧力容器、2はその内部に同心的に配置されたシュ
ラウド、3はシュラウド2内に配置された炉心、4はシ
ュラウド2上面を覆うシュラウドヘッド、5はシュラウ
ドヘッド上面 ・に設けた気水分離器、6はシュラウド
ヘッド4の下面に吊下設置されたオーバヘッドコアスプ
レィをそれぞれ示している。上記の構成において、炉心
3において発生した蒸気はシュラウドヘッド4を通過し
て気水分離器5に流入し、ここで水分を分前される。
(Prior Art) FIGS. 4 and 5 are a plan view and a vertical sectional view of a conventional overhead core spray. In each of these figures, 1 is a reactor pressure vessel, 2 is a shroud arranged concentrically inside the vessel, 3 is a reactor core arranged inside the shroud 2, 4 is a shroud head that covers the upper surface of the shroud 2, and 5 is a shroud head. The air/water separator provided on the upper surface of the shroud head, 6 indicates an overhead core spray installed suspended on the lower surface of the shroud head 4. In the above configuration, steam generated in the core 3 passes through the shroud head 4 and flows into the steam/water separator 5, where moisture is separated.

何らかの原因で炉心3の温度が急上昇すると、温度上昇
に伴い、炉心の構成部材特に燃料被覆管が溶損し、溶損
個所から漏出した核分裂生成物がタービン系等に混入す
るおそれがある。
If the temperature of the reactor core 3 suddenly rises for some reason, the core components, particularly the fuel cladding tubes, may be melted and damaged due to the rise in temperature, and there is a risk that fission products leaking from the melted portion may mix into the turbine system and the like.

上記のような事故を防止するため、炉心温度の急−上昇
時にはオーバヘッドコアスプレィ6を作動させて炉心を
緊急冷却し、核燃料被覆管の溶損を未然に防止するよう
にしている。
In order to prevent the above-mentioned accident, when the reactor core temperature suddenly rises, the overhead core spray 6 is activated to cool the reactor core urgently and to prevent nuclear fuel cladding from melting.

(発明が解決しようとする課題) 上記従来のオーバヘッドコアスプレィは、炉心で発生し
た蒸気が気水分離器5に流入する前に通過するシュラウ
ドヘッド4内に設けられている。
(Problems to be Solved by the Invention) The conventional overhead core spray described above is provided in the shroud head 4 through which steam generated in the reactor core passes before flowing into the steam separator 5.

このため、気水分離器5に流入する蒸気はオーバヘッド
コアスプレィ6の配管と直交して流れることとなり、気
水分離器5に流入する蒸気の流れに乱れを生じるだけで
なく、オーバヘッドコアスプレィ6に振動を生じるおそ
れがある。
Therefore, the steam flowing into the steam separator 5 flows perpendicularly to the piping of the overhead core spray 6, which not only causes turbulence in the flow of steam flowing into the steam water separator 5, but also causes the steam flowing into the overhead core spray 6 may cause vibration.

上記の振動によりオーバヘッドコアスプレィの溶接部に
クラック等の損傷を生じるおそれがあり、またシュラウ
ドヘッド4に対する吊下支持構造も損傷するおそれがあ
る。而して、それ等の損傷の進行状態によってはオーバ
ヘッドコアスプレィの落下を生じる。
The above vibration may cause damage such as cracks to the welded portion of the overhead core spray, and may also damage the suspension support structure for the shroud head 4. Depending on the progress of such damage, overhead core spray may fall.

そこで、オーバヘッドコアスプレィおよびその吊下支持
構造は定期的に点検することが必要であるが、その所在
部位が高レベルの放射線に曝露されているだけでなく、
検査対象が溶接部を土としているため検査作業がかなり
煩雑であり、作業員の被曝量が大きくなり好ましくない
。また、オーバヘッドコアスプレィの損傷の度合が大き
い場合には交換により更新するが、シュラウドヘッド、
オーバヘッドコアスプレィ、気水分離器は溶接による一
体構造であるため、仮りにオーバヘッドコアスプレィの
他は損傷がないかまたは使用上差し支えがない程度の損
傷しかない場合であっても、それ等全体を一体として交
換する必要があり、不必要に放射性廃棄物の量を増大さ
せる欠点があった。
Therefore, it is necessary to periodically inspect overhead core sprays and their suspended support structures, but not only are their locations exposed to high levels of radiation;
Since the inspection target is soil, which is the welded part, the inspection work is quite complicated, and the amount of radiation exposure to the workers increases, which is not preferable. In addition, if the damage to the overhead core spray is severe, it will be updated by replacing it, but the shroud head,
The overhead core spray and steam separator are integrally welded, so even if there is no damage other than the overhead core spray or there is only damage to the extent that it does not interfere with use, the entire It had to be replaced as a whole, which had the disadvantage of unnecessarily increasing the amount of radioactive waste.

本発明は上記の事情に基づきなされたもので、溶接部の
損傷を生じ難くするとともに検査作業を容易とし、放射
性廃棄物の発生量を最小限とすることができるオーバヘ
ッドコアスプレィを提供することを目的としている。
The present invention has been made based on the above circumstances, and an object of the present invention is to provide an overhead core spray that makes it difficult to damage welds, facilitates inspection work, and minimizes the amount of radioactive waste generated. The purpose is

[発明の構成] (課題を解決するための手段) 本発明のオーバヘッドコアスプレィは、原子炉炉心を包
囲するシュラウドとこのシュラウド上面を閉鎖するシュ
ラウドヘッドとの間に円筒シェル状のサポートリングを
挟圧支持固定し、このサポートリング内周面に円周方向
に分布した炉心軸方向剛性の大きな複数箇のサポート板
を設け、これ等のサポート板の先端に固定支持したこと
を特徴とする。
[Structure of the Invention] (Means for Solving the Problems) The overhead core spray of the present invention includes a cylindrical shell-shaped support ring sandwiched between a shroud that surrounds the reactor core and a shroud head that closes the upper surface of the shroud. A plurality of support plates having high rigidity in the axial direction of the core are provided on the inner circumferential surface of the support ring and are fixedly supported at the tips of these support plates.

(作用) 上記構成の本発明オーバヘッドコアスプレィは、前記サ
ポート板の剛性により振動力の上下方向成分に十分対抗
することができ、サポートリングの取付構造により横方
向および捻り方向成分に十分に対抗することができる。
(Function) The overhead core spray of the present invention having the above structure can sufficiently resist the vertical component of the vibration force due to the rigidity of the support plate, and can sufficiently resist the lateral and torsional components due to the mounting structure of the support ring. be able to.

さらに、本発明のオーバヘッドコアスプレィはシュラウ
ド、シュラウドヘッドとは独立した単体構成であるから
、損傷時にはそれのみを交換することができる。
Furthermore, since the overhead core spray of the present invention is a single unit structure independent of the shroud and the shroud head, only the shroud can be replaced in the event of damage.

(実施例) 第4図、第5図と同一部分には同一符号を付した第1図
は、本発明一実施例の横断面図、第2図はその縦断面図
である。これ等の図において、シュラウドヘッド4と炉
心3との間のシュラウドヘッド4の側壁には、円筒シェ
ル状のサポートリング7が係合され、サポートリング7
の上端面にはシュラウドヘッド4側壁上部に設けた段部
4aが当接され、サポートリング7の下端面はシュラウ
ド2上端のフランジ2a面に当接され、サポートリング
7はシュラウドヘッド4下面とシュラウド2上面との間
に挟持固定されている。前記オーバヘッドコアスプレィ
6は、サポートリング7の内周面に放射状に配置した複
数箇のサポート板8を介してサポートリング7に取り付
けられている。
(Embodiment) FIG. 1, in which the same parts as in FIGS. 4 and 5 are denoted by the same reference numerals, is a cross-sectional view of an embodiment of the present invention, and FIG. 2 is a longitudinal cross-sectional view thereof. In these figures, a cylindrical shell-shaped support ring 7 is engaged with the side wall of the shroud head 4 between the shroud head 4 and the reactor core 3.
A step 4a provided on the upper side wall of the shroud head 4 is in contact with the upper end surface, and a lower end surface of the support ring 7 is in contact with the flange 2a surface at the upper end of the shroud 2. 2 and the upper surface. The overhead core spray 6 is attached to the support ring 7 via a plurality of support plates 8 arranged radially on the inner peripheral surface of the support ring 7.

上記各サポート板8は、高さすなわちその原子炉圧力容
器、換言すれば炉心軸方向の寸法を大きくしその方向に
大きな剛性を有するものとしておく。
Each of the support plates 8 is designed to have a large height, that is, a dimension in the reactor pressure vessel, in other words, in the axial direction of the reactor core, and to have large rigidity in that direction.

上記構成の本発明オーバヘッドコアスプレィにおいては
、炉心3で発生した蒸気はオーバヘッドコアスプレィ6
を経由して気水分離器5に流入するに際して、蒸気の流
れの乱れによりオーバヘッドコアスプレィ6を振動させ
ようとする力が作用するが、前記の力の中の上下方向成
分に対しては前記サポート板8の高さ(原子炉圧力容器
軸方向寸法)を必要な大きさとすることにより十分に対
抗でき、横方向および捻り方向の成分に対してはサポー
トリング7をシュラウド2側壁およびシュラウドヘッド
4で固定する構造によって十分対抗することができる。
In the overhead core spray of the present invention having the above configuration, the steam generated in the reactor core 3 is transferred to the overhead core spray 6.
When the steam flows into the steam separator 5 via the steam flow, a force that tries to vibrate the overhead core spray 6 is applied due to the turbulence of the flow of steam, but the vertical component of the force is By setting the height of the support plate 8 (the axial dimension of the reactor pressure vessel) to the necessary size, sufficient resistance can be achieved. This can be adequately countered by a structure in which it is fixed in place.

前記各回と同一部分には同一符号を付した第3図は本発
明の他の実施例の縦断面図である。この実施例において
は、サポートリング7にはその上端にフランジ7aが設
けられ、このフランジを前記シュラウド2の上端のフラ
ンジ2aとシュラウドヘッド4のフランジ4bとの間に
挟持させて固定されている。この実施例にあっても、前
記第1図、第2図に示した実施例と同様の作用効果が得
られる。また、サポートリング7を挟圧するための段部
4aの加工を必要としないので、シュラウドヘッド4の
製作工数が削減できる。
FIG. 3 is a longitudinal sectional view of another embodiment of the present invention, in which the same parts as those in each case are given the same reference numerals. In this embodiment, the support ring 7 is provided with a flange 7a at its upper end, and this flange is sandwiched and fixed between the flange 2a at the upper end of the shroud 2 and the flange 4b of the shroud head 4. This embodiment also provides the same effects as the embodiments shown in FIGS. 1 and 2. Further, since there is no need to process the step portion 4a for pinching the support ring 7, the number of man-hours for manufacturing the shroud head 4 can be reduced.

[発明の効果] 上記から明らかなように、本発明のオーバヘッドコアス
プレィにおいては、蒸気通過時の振動力の上下方向成分
、横方向、捻れ方向成分の何れに対しても十分に対抗す
ることができ、各溶接部の損イ3を可及的に抑制するこ
とができる。また、オーバヘッドコアスプレィのみが単
体で取り外せるため、定期検査時等における検査作業が
容易であり1作業員の放射線被爆の減殺を図ることがで
きる。さらに、オーバヘッドコアスプレィがそれ自体独
立単体構成であるため、その損傷時にはそれのみを交換
することが可能であり、従来のように不必要に放射性廃
棄物を増大させるおそれはない。
[Effects of the Invention] As is clear from the above, the overhead core spray of the present invention is capable of sufficiently resisting all of the vertical, lateral, and torsional components of vibrational force when steam passes. This makes it possible to suppress losses at each welding part as much as possible. In addition, since only the overhead core spray can be removed individually, inspection work during periodic inspections is easy, and it is possible to reduce the radiation exposure of one worker. Furthermore, since the overhead core spray itself is an independent unit structure, it is possible to replace only it when it is damaged, and there is no risk of unnecessarily increasing radioactive waste as in the conventional case.

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

第1図は本発明一実施例の横断面図、第2図はその縦断
面図、第3図は他の実施例の縦断面図、第4図は従来例
の横断面図、第5図はその横断面図である。 1・・・・・・原子炉圧力容器 2・・・・・・シュラ
ウド 2a、4a、7a・・・・・・フランジ 3・・
・・・・炉心 4・・・・・・シュラウドヘッド 4b
・・・・・・段部 5・・・・・・気水分離器 6・・
・・・・オーバヘッドコアスプレィ 7・・。
FIG. 1 is a cross-sectional view of one embodiment of the present invention, FIG. 2 is a vertical cross-sectional view thereof, FIG. 3 is a vertical cross-sectional view of another embodiment, FIG. 4 is a cross-sectional view of a conventional example, and FIG. 5 is its cross-sectional view. 1... Reactor pressure vessel 2... Shroud 2a, 4a, 7a... Flange 3...
... Core 4 ... Shroud head 4b
...Stepped section 5...Steam water separator 6...
...Overhead Core Spray 7.

Claims (1)

【特許請求の範囲】[Claims] 原子炉炉心を包囲するシュラウドとこのシュラウド上面
を閉鎖するシュラウドヘッドとの間に円筒シェル状のサ
ポートリングを挟圧支持固定し、このサポートリング内
周面に円周方向に分布した炉心軸方向剛性の大きな複数
箇のサポート板を設け、これ等のサポート板の先端に固
定支持したことを特徴とするオーバヘッドコアスプレイ
A cylindrical shell-shaped support ring is clamped and fixed between the shroud that surrounds the reactor core and the shroud head that closes the upper surface of the shroud, and the core axial rigidity is distributed on the inner peripheral surface of the support ring in the circumferential direction. An overhead core spray characterized by having a plurality of large support plates fixedly supported at the tips of these support plates.
JP63138425A 1988-06-07 1988-06-07 Overhead core spray Pending JPH01307694A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP63138425A JPH01307694A (en) 1988-06-07 1988-06-07 Overhead core spray

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP63138425A JPH01307694A (en) 1988-06-07 1988-06-07 Overhead core spray

Publications (1)

Publication Number Publication Date
JPH01307694A true JPH01307694A (en) 1989-12-12

Family

ID=15221667

Family Applications (1)

Application Number Title Priority Date Filing Date
JP63138425A Pending JPH01307694A (en) 1988-06-07 1988-06-07 Overhead core spray

Country Status (1)

Country Link
JP (1) JPH01307694A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2002035551A1 (en) * 2000-10-20 2002-05-02 Framatome Anp Gmbh Device for cooling the core of a nuclear reactor

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2002035551A1 (en) * 2000-10-20 2002-05-02 Framatome Anp Gmbh Device for cooling the core of a nuclear reactor

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