JPH03591B2 - - Google Patents

Info

Publication number
JPH03591B2
JPH03591B2 JP58004006A JP400683A JPH03591B2 JP H03591 B2 JPH03591 B2 JP H03591B2 JP 58004006 A JP58004006 A JP 58004006A JP 400683 A JP400683 A JP 400683A JP H03591 B2 JPH03591 B2 JP H03591B2
Authority
JP
Japan
Prior art keywords
core
guide structure
coolant
reactor
control rod
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
JP58004006A
Other languages
Japanese (ja)
Other versions
JPS59128487A (en
Inventor
Eiji Yoshikawa
Minoru Ban
Minoru Komehana
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)

Description

【発明の詳細な説明】 本発明は、原子炉の構造に関する。[Detailed description of the invention] The present invention relates to the structure of a nuclear reactor.

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、出口ノズルへ向つて流
れ、原子炉容器から流出する。
In pressurized water type light water reactors that are commonly used in the past, the flow direction of the coolant that has ascended axially into the reactor core is changed radially outward (laterally) in the upper plenum directly above the core, and then flows through 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 is installed in this upper plenum to guide the control rod assembly of the reactor core.
It surrounds and protects the control rod assembly from direct exposure to the lateral flow of coolant.

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
が残つている。
However, if the number of control rods or aggregations of control rods is very large, the number of guide tubes will be large.
Alternatively, it is necessary to increase the size of the guide tube, 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 a risk of damage to the protection tubes due to fluid vibration due to 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 mainly provides a lower guide structure directly above the reactor core that individually surrounds and protects the control rod assemblies and has an assembly guide pipe that allows coolant to flow vertically upward. The gist of the invention is to provide a protection tube that individually surrounds the drive shaft of the rod assembly, and an upper guide structure that guides the coolant in the radial direction and directs it to the coolant outlet nozzle. Regardless of the increase, it is possible to suppress the increase in the number of protection tubes receiving the lateral flow of coolant, to ensure a sufficient coolant flow path, and to significantly improve the strength and soundness of the protection tubes.

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, which communicate with a primary cooling pipe (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。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 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. 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1
7が林設されて炉心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ツドによつて束状にされたも
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を流れ下つて下部プレナム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 1 are mounted on the core support plate 13.
7 are installed to form the reactor core 19. The fuel assembly 17 is a bundle of a large number of fuel rods and control rod guide tubes arranged in parallel by a support grid. The core support plate 13 includes a number of through holes (not shown) through which the coolant passes, and the coolant flows in from the inlet nozzle 3 as shown by the arrow, flows down the annular passage 11, and reaches 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。
An inner cylinder 21 supported above inside the core shell 9
constitutes a guide structure as described below.

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集合体
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 a lower part and an upper part.
An upper core plate 23 located directly above the reactor core 19 to position the fuel assembly 17, an intermediate support plate 25, a lower solid portion 27 of the inner cylinder 21, and an assembly guide tube 29 that individually surrounds the control rod assembly to be described later. constitutes the 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図に戻つて、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
穴をもつた内筒の上部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 again to FIG. 1, 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4
7,49によつ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 lid body 7. The control rods 31 of the control rod assembly 30 are inserted into the control rod guide tubes of the fuel assembly 17, and are connected to the drive device 4.
7 and 49 in a predetermined pattern to control the reactivity of the reactor core 19 during operation of the reactor.

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、該反応熱を吸収して昇
温し、案内管29内に流入し、上方へ流れる。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の穴を通つて出
口ノズル5から流出する。
As described above, the coolant that has entered the core 19 flows outside the fuel rods, absorbs the heat of reaction, increases its temperature, flows into the guide tube 29, and flows upward. It then passes over the intermediate support plate 25 into the upper plenum 51 where it changes direction and flows radially outward (laterally) and exits 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
方向に沿つて流れるので、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ほゞ同じ高
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 approximately the same height, the flow is smooth and there is little pressure loss, and even if the primary cooling system piping etc. is damaged due to some reason. 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 protective tubes 41 surround the drive shafts 35, which are much smaller than the control rods 31.
Despite having a large diameter and high strength and rigidity, the coolant flow path is large and allows 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 drawings]

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。
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...core.

Claims (1)

【特許請求の範囲】[Claims] 1 複数の燃料集合体よりなる炉心、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する下部案内構
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
なる原子炉において、前記下部案内構造体は、制
御棒集合体を個別に取り囲むと共に冷却材を鉛直
上方へ流す制御棒集合体用案内管、上部炉心板及
び前記案内管の群を取り囲む内筒を有し、前記上
部案内構造体は、前記制御棒集合体の駆動軸を個
別に取り囲む複数の保護管と同保護管の上下端を
支持する上部支持板及び中間支持板を有して冷却
材が横方向へ転向する上部プレナムを画成するこ
とを特徴とする原子炉。
1. A reactor core consisting of a plurality of fuel assemblies, a reactor core that encloses and supports the core in its lower part, and a reactor vessel that suspends and supports the core and forms a coolant descending annular space between the core and the core. , an upper lid body that closes the upper part of the vessel, a lower guide structure located directly above the core, an upper guide structure located above the lower guide structure, and an upper part of the vessel corresponding to the upper guide structure. In a nuclear reactor having a coolant nozzle provided on the side, the lower guide structure includes a control rod assembly guide tube that individually surrounds the control rod assemblies and allows the coolant to flow vertically upward; The upper guide structure has an inner cylinder surrounding an upper core plate and the group of guide tubes, and the upper guide structure supports a plurality of protection tubes individually surrounding the drive shaft of the control rod assembly and upper and lower ends of the protection tubes. A nuclear reactor having an upper support plate and an intermediate support plate defining an upper plenum in which coolant is laterally diverted.
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 JPS59128487A (en) 1984-07-24
JPH03591B2 true 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)

Families Citing this family (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
FR2595501B1 (en) * 1986-03-07 1988-06-10 Framatome Sa INTERNAL EQUIPMENT OF NUCLEAR REACTORS WITH EXTENDED TANK

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CH592352A5 (en) * 1974-03-20 1977-10-31 Commissariat Energie Atomique

Also Published As

Publication number Publication date
JPS59128487A (en) 1984-07-24

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