JPS59128487A - Reactor - Google Patents

Reactor

Info

Publication number
JPS59128487A
JPS59128487A JP58004006A JP400683A JPS59128487A JP S59128487 A JPS59128487 A JP S59128487A JP 58004006 A JP58004006 A JP 58004006A JP 400683 A JP400683 A JP 400683A JP S59128487 A JPS59128487 A JP S59128487A
Authority
JP
Japan
Prior art keywords
core
coolant
reactor
vessel
guide structure
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.)
Granted
Application number
JP58004006A
Other languages
Japanese (ja)
Other versions
JPH03591B2 (en
Inventor
英治 吉川
伴 實
米花 稔
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.)
Mitsubishi Heavy Industries Ltd
Original Assignee
Mitsubishi Heavy Industries 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 Mitsubishi Heavy Industries Ltd filed Critical Mitsubishi Heavy Industries Ltd
Priority to JP58004006A priority Critical patent/JPS59128487A/en
Publication of JPS59128487A publication Critical patent/JPS59128487A/en
Publication of JPH03591B2 publication Critical patent/JPH03591B2/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

Landscapes

  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Treatment Of Water By Oxidation Or Reduction (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】 従来一般的に用いられている加圧水型軽水炉では、炉心
を軸方向に上昇してきた冷却材は、炉心直上の上部プレ
ナム部で流れの方向が半径方向外方(横方向)に転換し
、出口ノズルへ向って流れ、原子炉容器から流出する。
[Detailed Description of the Invention] In conventional pressurized water type light water reactors, the coolant that has risen in the axial direction of the reactor core flows radially outward (laterally) in the upper plenum directly above the core. ) and flows towards the exit nozzle and out of the reactor vessel.

この上部プレナム部には、炉心の制御棒集合体を案内す
る案内管が設置されているが、これは、冷却材の前記横
向き流れに直接さらされないように、制御棒集合体を取
り囲んで、保護するものである。
A guide tube that guides the control rod assembly of the core is installed in this upper plenum, but this guide tube surrounds and protects the control rod assembly so that it is not directly exposed to the lateral flow of coolant. It is something to do.

しかるに、制御棒もしくはその集合体の数が非常に大き
いものでは、案内管の数が多数となり、又は案内管の大
きさを大きくする必要があり、出口ノズルに向う流路面
積を確保できなくなる。この問題を解決するために、炉
心出口直上に、冷却材を出口ノズルの方へ転回させるカ
ランドリア部を設置することが提案されているが、これ
は、制御棒をカランドリア部を上下につなぐ保護管の中
を通し、燃料集合体内に挿入されるようにし、制御棒を
冷却材横向き流れに直接さらされないようにしたもので
ある。しかし、このものでも、制御棒が多いと、保護管
が小径のものしか使用できず、半径方向流による流体振
動による保護管の破損、もしくはそれに伴なう制御棒の
破損のおそれが残っている。
However, if the number of control rods or their aggregates is very large, the number of guide tubes will be large or the size of the guide tubes will need to be increased, making it impossible to secure a flow path area toward the outlet nozzle. In order to solve this problem, it has been proposed to install a calandria section directly above the core exit that diverts the coolant toward the exit nozzle. The control rods are inserted through the fuel assembly into the fuel assembly so that the control rods are not directly exposed to the lateral flow of coolant. However, even in this case, if there are many control rods, only small-diameter protection tubes can be used, and there is still the risk of damage to the protection tubes due to fluid vibration caused by radial flow, or damage to the control rods due to this. .

本発明は、前述の問題に鑑みなされたものである。The present invention has been made in view of the above-mentioned problems.

すなわち、本発明は、主として制御棒集合体を個別に取
り囲んで保護すると共に、冷却材を鉛直上方へ流す集合
体案内管をもつ下部案内構造体を炉心の直上部に設け、
さらにその上方に制御棒集合体の駆動軸を個別に取り囲
む保護管を具えると共に冷却材を半径方向に向けて案内
し、冷却材出口ノズルへ向ける上部案内構造体を設けた
ことを要旨とし、これにより制御棒の増加にかかわらず
、冷却材横向き流れを受ける保護管の数の増大を抑制し
て、冷却材流路を十分確保でき、保護管の強度及び健全
性を著しく向上できる。
That is, the present invention provides a lower guide structure directly above the reactor core that mainly surrounds and protects the control rod assemblies individually and has an assembly guide pipe that allows coolant to flow vertically upward.
Furthermore, the gist is that an upper guide structure is provided above which protects tubes that individually surround the drive shafts of the control rod assembly, and guides the coolant in the radial direction and directs it toward the coolant outlet nozzle. As a result, regardless of the increase in the number of control rods, an increase in the number of protection tubes receiving a lateral flow of coolant can be suppressed, a sufficient coolant flow path can be secured, and the strength and soundness of the protection tubes can be significantly improved.

以下、本発明を図示の実施例に基づいて説明する。Hereinafter, the present invention will be explained based on illustrated embodiments.

第1図において、原子炉容器1は、上部に冷却材の入口
ノズル3と出口ノズル5が設けられ、これらは図示しな
い一次冷却系配管に連絡している。
In FIG. 1, a reactor vessel 1 is provided with a coolant inlet nozzle 3 and an outlet nozzle 5 at its upper part, and these communicate with a primary cooling system piping (not shown).

容器1は、ノズル3,5の下部で建屋に支持され、上部
は着脱自在の上蓋体7で閉じられる。
The container 1 is supported by a building at the lower part of the nozzles 3 and 5, and the upper part is closed with a removable upper lid body 7.

容器1の内部に垂下支持された炉心そう9は、容器1と
の間に冷却材が下降する環状流路11を画成し、下部に
下部炉心支持板13をもち、下方に下部プレナム15を
形成する。
The core shaft 9 suspended and supported inside the vessel 1 defines an annular flow path 11 through which the coolant descends between it and the vessel 1, has a lower core support plate 13 at the lower part, and a lower plenum 15 at the lower part. Form.

炉心支持板13の上には、多数の燃料集合体17が材膜
されて炉心19を構成する。燃料集合体17は、平行に
配置された多数の燃料棒と制御棒案内管とが支持グリッ
ドによって束状にされたものである。炉心支持板13は
、冷却材が通る多数の貫通孔(図示しない。)を具え、
冷却材は矢印に示すように入口ノズル3から流入し、環
状流路11を流れ下って下部プレナム15に至る。しか
る後に、炉心支持板13を貫通して炉心19に入る。
A large number of fuel assemblies 17 are mounted on the core support plate 13 to form a core 19 . The fuel assembly 17 is made up of a large number of parallelly arranged fuel rods and control rod guide tubes bundled together by a support grid. The core support plate 13 includes a large number of through holes (not shown) through which coolant passes,
The coolant enters from the inlet nozzle 3 as shown by the arrow and flows down the annular channel 11 to the lower plenum 15. Thereafter, it passes through the core support plate 13 and enters the core 19.

炉心そう9の内部上方に支持された内筒21は、後述す
るように案内構造体を構成する。
The inner cylinder 21 supported inside and above the core shell 9 constitutes a guide structure as described later.

案内構造体は、下部と上部に分けて認識され、炉心19
の直上に位置して燃料集合体17を位置決めする上部炉
心板23、中間支持板25、内筒21の下方中実部27
及び後述する制御棒案内管を個別に取り囲む集合体案内
管29が、下部案内構造体を構成する。
The guide structure is recognized as being divided into a lower part and an upper part, and is located in the core 19.
The upper core plate 23, the intermediate support plate 25, and the lower solid part 27 of the inner cylinder 21 are positioned directly above the fuel assembly 17.
And an assembly guide tube 29 that individually surrounds control rod guide tubes, which will be described later, constitutes a lower guide structure.

第2図は、制御棒集合体30の一例を示し、中性子吸収
材を含んだ複数の制御棒31の上端がスパイダ33及び
駆動軸35を介して一つの組立体として構成されている
FIG. 2 shows an example of a control rod assembly 30, in which the upper ends of a plurality of control rods 31 containing a neutron absorbing material are configured as one assembly via a spider 33 and a drive shaft 35.

再び第1図に戻って、駆動軸35を個々に取り囲む保護
管41は、中間支持板25、多数の流れ穴をもった内筒
の上部43及び上部支持板45と協働して上部案内構造
体を形成している。
Returning to FIG. 1 again, the protective tubes 41 that individually surround the drive shafts 35 cooperate with the intermediate support plate 25, the upper part 43 of the inner cylinder having a number of flow holes, and the upper support plate 45 to form an upper guide structure. forming the body.

制御棒集合体30は、多数あり、上蓋体7の上部に設け
た駆動装置47 、49に個別に連絡している。制御棒
集合体30の制御棒31は、燃料集合体17の制御棒案
内管に挿入され、駆動装置47 、49によって所定の
パターンで上下され、原子炉の運転中、炉心19の反応
度を制御する。
There are a large number of control rod assemblies 30, which are individually connected to drive devices 47 and 49 provided at the upper part of the upper cover body 7. The control rods 31 of the control rod assembly 30 are inserted into the control rod guide tube of the fuel assembly 17, and are moved up and down in a predetermined pattern by drive devices 47 and 49 to control the reactivity of the reactor core 19 during operation of the reactor. do.

前記したように、炉心19内に流入した冷却材は、燃料
棒の外側を流れ、核反応熱を吸収して昇温し、案内管2
9内に流入し、上方へ流れる。
As described above, the coolant that has flowed into the core 19 flows outside the fuel rods, absorbs the heat of the nuclear reaction, increases its temperature, and flows through the guide tubes 2.
9 and flows upward.

更に、中間支持板25を越えて上部プレナム51へ至り
、ここで方向を変えて半径方向外方(横方向)へ流れ、
内筒21の上部43の穴を通って出口ノズル5から流出
する。
Furthermore, it passes over the intermediate support plate 25 and reaches the upper plenum 51, where it changes direction and flows radially outward (laterally).
It flows out from the outlet nozzle 5 through a hole in the upper part 43 of the inner cylinder 21.

以上の本実施例によれば、細いすなわち剛性の小さい制
御棒31のまわりでは、冷却材はその軸方向に沿って流
れるので、流体振動を生ずることがなく、振動による摩
耗が防止される。
According to this embodiment, the coolant flows along the axial direction around the control rod 31, which is thin, that is, has low rigidity, so that no fluid vibration occurs and wear due to vibration is prevented.

又、冷却材は、上部案内構造体からはソ同じ高さにある
出口ノズル5に流れ、流出するので、流れがスムースで
圧力損失が少ない上に、例え何らかの原因により一次冷
却系配管等に破損が生じても、容器1内で冷却材が自然
循環し、炉心19の冷却を確保できる。
In addition, since the coolant flows from the upper guide structure to the outlet nozzle 5 located at the same height as the upper guide structure, the flow is smooth and there is little pressure loss. Even if this occurs, the coolant circulates naturally within the vessel 1, and cooling of the core 19 can be ensured.

更に又、上昇した冷却材が横向き流れとなる上部プレナ
ム51では、保護管41が制御棒31に比して格段に少
ない駆動軸35を取り囲むので、径を大きくして強度剛
性が大きいにもかかわらず、冷却材の流路が大きくこれ
をスムースに流すことができる。
Furthermore, in the upper plenum 51 where the ascending coolant flows sideways, the protection tube 41 surrounds the drive shaft 35, which is much smaller in number than the control rod 31, so even though the diameter is large and the strength and rigidity are large, First, the coolant flow path is large, allowing the coolant to flow smoothly.

更にこのため、保護管41に作用する流体力も小さいの
で、励振力も小さく、健全性が高い。
Furthermore, because of this, the fluid force acting on the protection tube 41 is also small, so the excitation force is also small and the integrity is high.

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

第1図は、本発明の実施例を示す縦断面図、第2図は前
記実施例の1構成部材を示す側面図である。 1・・・原子炉容器、9・・・炉心そう、17・・・燃
料集合体、19・・炉心 図面のイ;司0;(内容に変更なし) 第1図 手続補正書(方式) 昭和58年 5月10日 事件の表示 昭和58  年    特 許 願第   4006 
  号発明の名称 原子炉 補正をする名 事件との関係 特許出願人 住  所    東京都千代田区丸の内二丁目5番1号
名 称(620)三菱重工業株式会社 代  理  人 住  所    東京都千代田区丸の内二丁目5@11
3(内容変更なし7)を添付します。
FIG. 1 is a longitudinal sectional view showing an embodiment of the present invention, and FIG. 2 is a side view showing one component of the embodiment. 1...Reactor vessel, 9...Reactor core, 17...Fuel assembly, 19...Reactor core drawing A; Tsukasa 0; (No change in content) Figure 1 procedural amendment (method) Showa Indication of the May 10, 1958 incident Patent Application No. 4006 of 1982
Relationship with famous cases that amend the name of the invention No. 2 Nuclear Reactor Patent Applicant Address 2-5-1 Marunouchi, Chiyoda-ku, Tokyo Name (620) Representative of Mitsubishi Heavy Industries, Ltd. Person Address 2 Marunouchi, Chiyoda-ku, Tokyo Chome 5@11
3 (No change in content 7) is attached.

Claims (1)

【特許請求の範囲】[Claims] 複数の燃料集合体よシなる炉心、該炉心を下部に内包し
て支持する炉心そう、該炉心そうを内部に垂下支持し該
炉心そうとの間に冷却材下降環状空間を形成する原子炉
容器、該容器の上部を閉じる上蓋体、該炉心の直上に位
置し制御棒集合体用案内管を含む下部案内構造体、該下
部案内構造体の上部に位置する上部案内構造体及び該上
部案内構造体に対応して該容器の上方側部に設けられた
冷却材用ノズルを有してなることを特徴とする原子炉。
A reactor core consisting of a plurality of fuel assemblies, a reactor core containing and supporting the core in its lower part, and a reactor vessel that suspends and supports the reactor core inside and forms a coolant descending annular space between the reactor core and the reactor core. , an upper lid body that closes the upper part of the vessel, a lower guide structure located directly above the core and including a control rod assembly guide tube, an upper guide structure located above the lower guide structure, and the upper guide structure. A nuclear reactor, characterized in that it has a coolant nozzle provided on the upper side of the vessel in correspondence with the vessel.
JP58004006A 1983-01-13 1983-01-13 Reactor Granted JPS59128487A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58004006A JPS59128487A (en) 1983-01-13 1983-01-13 Reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58004006A JPS59128487A (en) 1983-01-13 1983-01-13 Reactor

Publications (2)

Publication Number Publication Date
JPS59128487A true JPS59128487A (en) 1984-07-24
JPH03591B2 JPH03591B2 (en) 1991-01-08

Family

ID=11572891

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58004006A Granted JPS59128487A (en) 1983-01-13 1983-01-13 Reactor

Country Status (1)

Country Link
JP (1) JPS59128487A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS59212795A (en) * 1983-05-16 1984-12-01 ウエスチングハウス エレクトリツク コ−ポレ−シヨン Reactor
JPS62273493A (en) * 1986-03-07 1987-11-27 フラマト−ム Nuclear reactor

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS50132398A (en) * 1974-03-20 1975-10-20

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS50132398A (en) * 1974-03-20 1975-10-20

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS59212795A (en) * 1983-05-16 1984-12-01 ウエスチングハウス エレクトリツク コ−ポレ−シヨン Reactor
JPH0464038B2 (en) * 1983-05-16 1992-10-13 Westinghouse Electric Corp
JPS62273493A (en) * 1986-03-07 1987-11-27 フラマト−ム Nuclear reactor

Also Published As

Publication number Publication date
JPH03591B2 (en) 1991-01-08

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