JPS5853790A - Core structure - Google Patents
Core structureInfo
- Publication number
- JPS5853790A JPS5853790A JP56150628A JP15062881A JPS5853790A JP S5853790 A JPS5853790 A JP S5853790A JP 56150628 A JP56150628 A JP 56150628A JP 15062881 A JP15062881 A JP 15062881A JP S5853790 A JPS5853790 A JP S5853790A
- Authority
- JP
- Japan
- Prior art keywords
- fuel assembly
- fuel
- coolant
- injection system
- reactor core
- 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
Links
Classifications
-
- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Magnetic Heads (AREA)
- Fuel-Injection Apparatus (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】
本発明は、原子炉の炉心構造に係り、特に冷却材喪失事
故時における炉心の冷却に好適な炉心構造に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a core structure of a nuclear reactor, and particularly to a core structure suitable for cooling a reactor core in the event of a loss of coolant accident.
第１図に、沸騰水ｌＪ＆原子炉の工学的安全設備の概要
を示す。工学的安全設置は、再循環配管３の破断などで
、多数の燃料集合体１で構成される炉心から冷却材が喪
失した場合に作動し燃料の過熱を防ぐためのものである
。工学的安全設備の一系統である注水系２は、シュラウ
ドｌｉ４に冷却材注入口を設は燃料果合体１の側面から
、燃料果合体ｌ同士のすきま領域（以下、バイパス領域
と呼ぶ）に冷却材を注入するものである。第２図は、炉
心内の燃料果合体ｌの配列を示したものである。燃料果
合体１は、炉心の上部に設けられた上部格子板１２で区
切られた矩形の各領域内に４体が装荷されている。そし
て、この４体の燃料果合体１によって十字形のバイパス
領域が形成される。このバイパス領域は、原子炉の出力
をＡ整するための制御棒１２が上下する。第２図に示し
た燃料果合体ｌの配列１ｉ１？面で示したものが、第３
図である。Figure 1 shows an overview of the engineering safety equipment for boiling water lJ and nuclear reactors. The engineering safety installation is activated in the event that coolant is lost from the core, which is made up of a large number of fuel assemblies 1, due to a break in the recirculation pipe 3, etc., and is intended to prevent the fuel from overheating. The water injection system 2, which is a system of engineering safety equipment, has a coolant inlet in the shroud li4, and cools it from the side of the fuel assembly 1 into the gap area between the fuel assembly 1 (hereinafter referred to as the bypass area). The material is injected. FIG. 2 shows the arrangement of fuel assembly l in the reactor core. Four fuel product combinations 1 are loaded in each rectangular area separated by an upper lattice plate 12 provided at the top of the reactor core. A cross-shaped bypass area is formed by these four fuel fruit combinations 1. In this bypass region, the control rod 12 for adjusting the output of the nuclear reactor moves up and down. Arrangement 1i1 of the fuel assembly l shown in FIG. 2? The one shown in the figure is the third
It is a diagram.
再循環配管破断の事故時には、原子炉を停止するために
制−棒１２が全挿入される。そして注水系２の作動によ
り燃料果合体ｌで囲まれたバイパス領域２１に冷却材が
注入される。注入された冷却材は、バイパス領域２１か
ら下部プレナムに流入する。しかしバイパス領域２１と
下部プレナムを結ぶ流路面積は小さいので、注入された
冷却材は下部プレナムに流入するとともに、バイパス領
域を満し燃料集合体ｌの上端から燃料集合体内へ溢流す
る。炉心の健全性の面からは、燃料果合体内に冷却材が
流入し、発熱体である撚科棒を冷却することが好都合で
ある。しかし、注水系２によって注入される冷却材が燃
料集会体上端から溢流入し始めるにはバイパス領域２１
全体を満水にしてやらねばならず、この時間を短縮すれ
ば、事故時における炉心の健全性はさらに促進すること
ができる。In the event of an accident in which the recirculation pipe ruptures, the control rod 12 is fully inserted to shut down the reactor. By operating the water injection system 2, coolant is injected into the bypass region 21 surrounded by the fuel assembly 1. The injected coolant flows from the bypass region 21 into the lower plenum. However, since the flow path area connecting the bypass region 21 and the lower plenum is small, the injected coolant flows into the lower plenum, fills the bypass region, and overflows into the fuel assembly from the upper end of the fuel assembly l. From the standpoint of core integrity, it is advantageous for coolant to flow into the fuel assembly to cool the heating elements, the twisted rods. However, in order for the coolant injected by the water injection system 2 to start overflowing from the upper end of the fuel assembly, the bypass area 21
The entire reactor must be filled with water, and reducing this time can further promote the health of the core in the event of an accident.
本発明は、注水系からの冷却材がバイパス領域から燃料
集合体へ６ｉ流を開始する時間を早めて。The present invention accelerates the time at which coolant from the water injection system begins to flow from the bypass region to the fuel assembly.
事故時における炉心の健全性をさらに促進する炉心構造
を提供することを目的とする。The purpose is to provide a core structure that further promotes core integrity in the event of an accident.
本発明は、バイパス領域において注水系入口よりも低い
位置にせきを設けて、バイパス領域満水以前に燃料集合
体上端よシ冷却材を溢流を開始させるようにしたもので
ある。According to the present invention, a weir is provided in the bypass region at a position lower than the water injection system inlet, so that the coolant starts overflowing from the upper end of the fuel assembly before the bypass region is filled with water.
本発明の一実施例を、第４図に示す。これは、バイパス
領域において注水系２の入口よシ低い位置に、流路面積
を小さくするせき３１．３２を設けたものである。上部
格子板１１の下のバイパス領域には、上部格子板工１か
ら支え３３を下にのばし、バイパス領域の形状に合わせ
、燃料果合体１とのすきまが、わずかにあくせき３１を
つける。An embodiment of the present invention is shown in FIG. This is because weirs 31 and 32 are provided in the bypass area at a lower position than the inlet of the water injection system 2 to reduce the area of the flow path. In the bypass area under the upper lattice plate 11, a support 33 is extended downward from the upper lattice plate work 1, and a slight gap 31 is created between it and the fuel assembly 1 in accordance with the shape of the bypass area.
また、制御棒１２が上下するバイパス領域には、燃料果
合体１に制御棒１２とのすきまを小さくするせき３２を
取付ける。上部格子板１１の下に支え３３およびせき３
１を取り付けた鳥かん図を第５図に示す。また燃料集合
体１にせき３２を取り付けた鳥かん図を第６図に、上面
図を第７図に示す。本実施例によれば、燃料集合体の制
御棒側の面にせきが取付けられていることから、燃料交
換の際の組込み方向の誤シがなくなるという効果がある
。Further, in the bypass area where the control rod 12 moves up and down, a weir 32 is attached to the fuel assembly 1 to reduce the gap between it and the control rod 12. A support 33 and a weir 3 are provided under the upper lattice plate 11.
Figure 5 shows the bird's eye diagram with 1 attached. Further, a bird's eye view of the fuel assembly 1 with the weir 32 attached is shown in FIG. 6, and a top view is shown in FIG. 7. According to this embodiment, since the weir is attached to the surface of the fuel assembly on the control rod side, there is an effect that there is no error in the installation direction during fuel exchange.
本発明によれば、冷却材喪失事故時に注水系から冷却材
が注水された場合、せきから上のバイパス領域だけを満
水にすれば、燃料果合体上端から溢流する。そのため、
従来技術のようにバイパス領域全体を満水にする必要が
なく、溢流を開始する時間が早くなる。そして事故初期
においては。According to the present invention, when coolant is injected from the water injection system during a coolant loss accident, if only the bypass area above the weir is filled with water, it will overflow from the upper end of the fuel assembly. Therefore,
It is not necessary to fill the entire bypass area with water as in the prior art, which speeds up the time to initiate overflow. And in the early stages of the accident.
発熱体である燃料集合体内に流入する冷却材量が多くな
り、炉心の健全性がさらに促進される。The amount of coolant flowing into the fuel assembly, which is a heating element, is increased, further promoting the health of the reactor core.
第１図は原子炉の概要説明図、第２図は炉心の構造を示
す鳥かん図、ＪＥ３図は第２図の断面図、第４図は本発
明の実施例を示す＃？画図、第５図は第４図の一部を示
す鳥かん図、第６図は第４図の一部を示す鳥かん図、第
７図は第６図の上面図である。
１・・・燃料集合体、１工・・・上部格止格、３１・・
・せき、第２ 目
／
第３ 口
１
１
＄４ 固
２
茅、５″目
茅を目
第、７目Fig. 1 is a schematic explanatory diagram of a nuclear reactor, Fig. 2 is a bird's eye diagram showing the structure of the reactor core, Fig. JE3 is a sectional view of Fig. 2, and Fig. 4 shows an embodiment of the present invention. 5 is a bird's eye diagram showing a part of FIG. 4, FIG. 6 is a bird's eye diagram showing a part of FIG. 4, and FIG. 7 is a top view of FIG. 1...Fuel assembly, 1 construction...Upper rating, 31...
・Cough, 2nd eye / 3rd mouth 1 1 $4 Hard 2 Kaya, 5″ eyes Kaya eye, 7th eye
Claims (1)
構成される燃料果合体を１間隔を持って配列し炉心を構
成し、かつ事故時に炉心に冷却水を注入する注入系をＭ
する原子炉において、注入系入口よシ低い位置で、燃料
系合体同士のすきまの部分に流路断面積ヲ小さくするせ
きを設けたことを＠＃とする炉心構造。1. M is an injection system that constructs a reactor core by arranging fuel assembly, which is made up of fuel tanks filled with nuclear fuel in a box with a rectangular cross section, at one interval, and injects cooling water into the reactor core in the event of an accident.
A reactor core structure in which a weir is provided in the gap between the fuel system combinations to reduce the cross-sectional area of the flow path at a position lower than the injection system inlet.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56150628A JPS5853790A (en) | 1981-09-25 | 1981-09-25 | Core structure |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56150628A JPS5853790A (en) | 1981-09-25 | 1981-09-25 | Core structure |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS5853790A true JPS5853790A (en) | 1983-03-30 |
Family
ID=15501009
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP56150628A Pending JPS5853790A (en) | 1981-09-25 | 1981-09-25 | Core structure |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5853790A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO1987002805A1 (en) | 1985-11-02 | 1987-05-07 | Nippon Hoso Kyokai | Hierarchical data processing system |
| JPH04106686A (en) * | 1990-08-27 | 1992-04-08 | Nec Corp | Input area adaptive neural network character recognizing device |
-
1981
- 1981-09-25 JP JP56150628A patent/JPS5853790A/en active Pending
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO1987002805A1 (en) | 1985-11-02 | 1987-05-07 | Nippon Hoso Kyokai | Hierarchical data processing system |
| US5058184A (en) * | 1985-11-02 | 1991-10-15 | Nippon Hoso Kyokai | Hierachical information processing system |
| JPH04106686A (en) * | 1990-08-27 | 1992-04-08 | Nec Corp | Input area adaptive neural network character recognizing device |
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