JPH057679B2 - - Google Patents

Info

Publication number
JPH057679B2
JPH057679B2 JP62194507A JP19450787A JPH057679B2 JP H057679 B2 JPH057679 B2 JP H057679B2 JP 62194507 A JP62194507 A JP 62194507A JP 19450787 A JP19450787 A JP 19450787A JP H057679 B2 JPH057679 B2 JP H057679B2
Authority
JP
Japan
Prior art keywords
fuel
coolant
support fitting
orifice
flow path
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
JP62194507A
Other languages
Japanese (ja)
Other versions
JPS6438691A (en
Inventor
Norinobu Yokota
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
Tokyo Shibaura Electric Co 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 Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP62194507A priority Critical patent/JPS6438691A/en
Publication of JPS6438691A publication Critical patent/JPS6438691A/en
Publication of JPH057679B2 publication Critical patent/JPH057679B2/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)

Description

【発明の詳細な説明】 「産業上の利用分野」 この発明は、沸騰水型原子炉に適用される中心
部燃料支持金具に係り、特に燃料集合体を異物に
よる破損から防止するようにした中心部燃料支持
金具に関する。
DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] This invention relates to a center fuel support fitting applied to a boiling water nuclear reactor, and in particular to a center fuel support fitting for preventing fuel assemblies from being damaged by foreign objects. Regarding fuel support fittings.

「従来の技術」 沸騰水型原子炉では、多数の燃料集合体が装荷
されて原子炉炉心が構成される。燃料集合体は第
4図に示すように、角筒状のチヤンネルボツクス
1内管に多数の燃料棒2がスペーサ3によつて所
定の間隔に保持され、収容されたものである。各
燃料棒2の上下両端部は、上部タイプレート4お
よび下部タイプレート5によつてそれぞれ拘束さ
れ固定される。
"Prior Art" In a boiling water nuclear reactor, a reactor core is constructed by loading a large number of fuel assemblies. As shown in FIG. 4, the fuel assembly has a large number of fuel rods 2 held at predetermined intervals by spacers 3 and housed in the inner tube of a channel box 1 having a rectangular cylindrical shape. Both upper and lower ends of each fuel rod 2 are restrained and fixed by an upper tie plate 4 and a lower tie plate 5, respectively.

このうち、下部タイプレート5は、タイプレー
ト本体6と燃料棒支持部7とが一体成形されて構
成される。各燃料棒2の下部端栓8は、燃料棒支
持部7の孔9に嵌合または螺合されて拘束され
る。さらに、燃料棒支持部7には、冷却材流路1
0が形成される。また、タイプレート本体6の下
端部には冷却材流入口11が開口され、この冷却
材流入口11から流入した冷却材は冷却材流路1
0を通過してチヤンネルボツクス1内に案内され
る。
Among these, the lower tie plate 5 is constructed by integrally molding a tie plate main body 6 and a fuel rod support portion 7. The lower end plug 8 of each fuel rod 2 is fitted or screwed into a hole 9 of the fuel rod support 7 and restrained. Furthermore, the fuel rod support section 7 includes a coolant flow path 1.
0 is formed. A coolant inlet 11 is opened at the lower end of the tie plate main body 6, and the coolant flowing from the coolant inlet 11 flows into the coolant flow path 1.
0 and is guided into channel box 1.

燃料集合体は炉心支持板状に取り付けられた燃
料支持金具に嵌合し、下端を位置決めされかつ重
量を保持されるとともに上部格子板により燃料集
合体上部の位置決めをされる。
The fuel assembly is fitted into a fuel support fitting attached to the core support plate, the lower end is positioned and the weight is held, and the upper part of the fuel assembly is positioned by the upper grid plate.

燃料支持金具には中心部燃料支持金具と周辺部
燃料支持金具の2種類がある。中心部燃料支持金
具12は第5図が示すように、中心部に制御棒を
通す十字の溝13があり、その回りは、4つの燃
料集合体を保持するために4つの室に別れ、それ
ぞれの室の頂部には燃料集合体と嵌合する燃料支
持穴14がある。各室の下部の側面には冷却材の
入口穴15がある。
There are two types of fuel support fittings: central fuel support fittings and peripheral fuel support fittings. As shown in FIG. 5, the center fuel support fitting 12 has a cross-shaped groove 13 in the center for passing the control rod, and the area around it is divided into four chambers for holding four fuel assemblies. At the top of the chamber is a fuel support hole 14 that mates with the fuel assembly. There is a coolant inlet hole 15 in the lower side of each chamber.

周辺部燃料支持金具は、図示しないが、円筒形
をしており、上部で1つの燃料集合体を保持し、
下部より冷却材が入る構造となつている。周辺部
燃料支持金具は炉心最外周の一部に採用されてい
る。他の部分は中心部燃料支持金具である。
Although not shown, the peripheral fuel support fitting has a cylindrical shape, holds one fuel assembly at the upper part,
The structure is such that the coolant enters from the bottom. Peripheral fuel support fittings are installed on a part of the outermost periphery of the core. The other part is the center fuel support fitting.

中心部燃料支持金具12の下部の円筒部12a
には制御棒案内管の上部が連結される。制御棒案
内管には冷却材を通すための穴があいており、こ
の穴と中心部燃料支持金具12の下部の冷却材入
口穴15とが対応している。
Lower cylindrical portion 12a of central fuel support fitting 12
The upper part of the control rod guide tube is connected to the upper part of the control rod guide tube. The control rod guide tube has a hole through which coolant passes, and this hole corresponds to a coolant inlet hole 15 in the lower part of the central fuel support fitting 12.

「発明が解決しようとする問題点」 ところで、原子炉の定期点検中には、原子炉圧
力容器の上部の蓋を開けて燃料集合体の交換を行
つている。この点検作業中には、作業に使用した
針金等の金属片が原子炉圧力容器内管に落下する
ことがある。また、原子炉構造物が酸化または他
の原因で一部剥離し、この剥離片が原子炉圧力容
器内に同様に落下することもある。これらの金属
片や剥離片等の異物は通常重量が小さいために、
原子炉運転中に冷却材の流動に伴つて炉心へ導か
れ、その一部が冷却材とともに制御棒案内管上部
の穴より流入する。流入した冷却材と異物は中心
部燃料支持金具12に入る。また周辺部燃料支持
金具では冷却材入口穴15より入ることにより、
異物は燃料集合体の下部タイプレート5に流入
し、燃料棒支持部7の冷却材流路10を通過す
る。この冷却材流路10は流路面積が広いので大
きな異物以外は引掛からず、流路面積の最も狭い
スペーサ3部に小さな異物が引掛かる可能性が高
い。
``Problems to be Solved by the Invention'' By the way, during periodic inspections of nuclear reactors, the top cover of the reactor pressure vessel is opened to replace the fuel assembly. During this inspection work, metal pieces such as wire used in the work may fall into the reactor pressure vessel inner pipe. Additionally, parts of the reactor structure may become detached due to oxidation or other causes, and these detached pieces may similarly fall into the reactor pressure vessel. These foreign objects such as metal pieces and flakes are usually small in weight, so
During reactor operation, coolant is guided into the reactor core as it flows, and a portion of it flows together with the coolant through holes in the upper part of the control rod guide tubes. The incoming coolant and foreign matter enter the center fuel support fitting 12. In addition, in the peripheral fuel support fitting, by entering from the coolant inlet hole 15,
The foreign matter flows into the lower tie plate 5 of the fuel assembly and passes through the coolant passage 10 of the fuel rod support 7. Since the coolant flow path 10 has a wide flow path area, only large foreign objects will be caught, and there is a high possibility that small foreign objects will be caught in the spacer 3 portion having the narrowest flow path area.

一方、集合体内に流入した冷却材は、下部タイ
プレート5やスペーサ3等で流れが乱されたり、
燃料集合体の上部でボイドが発生する等のために
局所的に流速が変化する。この流速の変化等の影
響によつて、異物と燃料棒2が微小振動してい
る。
On the other hand, the flow of the coolant flowing into the assembly is disturbed by the lower tie plate 5, spacer 3, etc.
The flow velocity changes locally due to voids occurring in the upper part of the fuel assembly. Due to the influence of this change in flow velocity, etc., the foreign matter and the fuel rod 2 are slightly vibrating.

万一、この振動する異物と燃料棒2が当接する
と、フレツテイング現象が発生するおそれがあ
る。
If this vibrating foreign object were to come into contact with the fuel rod 2, there is a possibility that a fretting phenomenon would occur.

このフレツテイング現象は、金属片等の異物
が、振動する燃料棒2の被覆管に当接この被覆管
に付着した腐食膜を剥離させ、この剥離部が新た
に腐食され、これらの剥離と腐食との相乗作用に
より被覆管の浸食が進行する現象である。このフ
レツテイング現象が進むと、燃料棒2の被覆管に
孔が開き、この孔から燃料棒2内に冷却材が侵食
する。この侵食した冷却材と被覆管内面等が反応
して水素化物が生成され、被覆管が破損する。こ
のような被覆管の破損により、燃料棒2内の放射
能が冷却材中に多量に拡散し、原子炉の安全性が
損なわれる恐れがある。
This fretting phenomenon occurs when a foreign object such as a metal piece comes into contact with the cladding tube of the vibrating fuel rod 2 and peels off the corrosion film attached to the cladding tube, and this peeled part becomes newly corroded, resulting in this peeling and corrosion. This is a phenomenon in which erosion of the cladding progresses due to the synergistic action of As this fretting phenomenon progresses, a hole opens in the cladding tube of the fuel rod 2, and the coolant erodes into the fuel rod 2 through this hole. This eroded coolant reacts with the inner surface of the cladding tube, and hydrides are generated, causing damage to the cladding tube. Such damage to the cladding tube may cause a large amount of radioactivity within the fuel rods 2 to diffuse into the coolant, which may impair the safety of the nuclear reactor.

この発明は、上記事実を考慮してなされたもの
であり、燃料棒の健全性を維持して原子炉の安全
性を向上させることができる中心部燃料支持金具
を提供することを目的とする。
The present invention has been made in consideration of the above facts, and an object of the present invention is to provide a central fuel support fitting that can maintain the integrity of fuel rods and improve the safety of a nuclear reactor.

「問題点を解決するための手段」 上記目的を達成するために、この発明に係る中
心部燃料支持金具は、冷却材流路の入口部にオリ
フイスを有し、そのオリフイスの上流側に網状の
異物捕獲部材を取り付けている。そして、オリフ
イスで流量を決定し、網状の異物捕獲部材で異物
を捕獲するようにして、燃料集合体に異物が流入
しないようにしている。
"Means for Solving the Problems" In order to achieve the above object, the central fuel support fitting according to the present invention has an orifice at the entrance of the coolant flow path, and a net-like structure on the upstream side of the orifice. A foreign object capture member is attached. The orifice determines the flow rate, and the net-like foreign matter capturing member captures foreign matter to prevent foreign matter from flowing into the fuel assembly.

「実施例」 以下、この発明の一実施例を図面に基づいて説
明する。
"Embodiment" An embodiment of the present invention will be described below based on the drawings.

第3図に示すように、沸騰水型原子炉の原子炉
圧力容器21内には、炉心22が収容されるとと
もに、冷却材が充填される。
As shown in FIG. 3, a reactor pressure vessel 21 of a boiling water reactor accommodates a reactor core 22 and is filled with coolant.

炉心22は炉心シユラウドによつて取り囲まれ
ている。炉心シユラウドは円筒状で、冷却材を炉
心22内の上向きの流れと、その外側の環状部を
下向きに流れる再循環流とに分離する。再循環流
は原子炉圧力容器外部の再循環ポンプと内部のジ
エツトポンプにより昇圧され、炉心下部プレムナ
部23へ送られる。昇圧された冷却材は炉心下部
の制御棒駆動機構ハウジング24や制御棒案内管
25の間を上昇するが、炉心支持板26に遮ぎら
れ、炉心下部プレムナ部23よりの出口に相当す
る制御棒案内管25の上部にある側穴を経由して
中心部燃料支持金具27へ導かれる。一部の冷却
材については周辺部燃料支持金具に直接入る。
Core 22 is surrounded by a core shroud. The core shroud is cylindrical and separates the coolant into an upward flow within the core 22 and a recirculation flow downward through its outer annulus. The recirculation flow is pressurized by a recirculation pump outside the reactor pressure vessel and a jet pump inside the reactor pressure vessel, and is sent to the lower core plenum 23. The pressurized coolant rises between the control rod drive mechanism housing 24 and the control rod guide tube 25 in the lower part of the core, but is blocked by the core support plate 26, and the coolant rises between the control rod drive mechanism housing 24 and the control rod guide tube 25 in the lower part of the core, and is blocked by the core support plate 26. The fuel is guided to the central fuel support fitting 27 via a side hole in the upper part of the guide tube 25 . Some coolant goes directly into the peripheral fuel support fittings.

中心部燃料支持金具27の構成を第1図および
第2図に示す。中心部燃料支持金具27の冷却材
入口穴28部には燃料集合体29への冷却材量が
適正になるように流れを絞るオリフイス30が取
りつけてある。オリフイス30には内径の異なる
種類がいくつかあり、これを変えると燃料集合体
29への冷却材流量を変えられるようになつてい
る。オリフイス30の前面にあたる制御棒案内管
の側穴31はオリフイス30に比べると穴径が大
きく、オリフイス30が効果的に働くようになつ
ている。またオリフイス30後の冷却材流路32
の穴径についても同様に大きくなつている。
The configuration of the central fuel support fitting 27 is shown in FIGS. 1 and 2. An orifice 30 is attached to the coolant inlet hole 28 of the central fuel support fitting 27 to restrict the flow so that the amount of coolant flowing into the fuel assembly 29 is appropriate. There are several types of orifices 30 with different inner diameters, and by changing this, the flow rate of coolant to the fuel assembly 29 can be changed. The side hole 31 of the control rod guide tube, which is located in front of the orifice 30, has a larger hole diameter than the orifice 30, so that the orifice 30 can work effectively. Also, the coolant flow path 32 after the orifice 30
Similarly, the hole diameter has also increased.

中心部燃料支持金具27のオリフイス30に
は、異物捕獲部材としての金網33が設置され
る。このような金網33が配設されたことによ
り、冷却材中の金属片や剥離片等の異物が冷却材
とともに流入しても金網33に引掛かり捕獲され
ることになる。その結果、原子炉運転中に燃料棒
の存在するチヤンネルボツクス内へ異物が流入す
ることがなく、燃料棒のフレツテイング現象によ
る破損が防止される。そのため、燃料棒の健全性
を維持することができるとともに、原子炉の安全
性を向上させることができる。
A wire mesh 33 serving as a foreign matter capturing member is installed in the orifice 30 of the central fuel support fitting 27 . By disposing such a wire mesh 33, even if foreign objects such as metal pieces or peeled pieces in the coolant flow in together with the coolant, they will be caught by the wire mesh 33 and captured. As a result, foreign matter does not flow into the channel box where the fuel rods are located during the operation of the nuclear reactor, and damage to the fuel rods due to fretting phenomenon is prevented. Therefore, the integrity of the fuel rods can be maintained, and the safety of the nuclear reactor can be improved.

「発明の効果」 以上のように、この発明に係る中心部燃料支持
金具によれば、オリフイスの上流側に網状の異物
捕獲部材が取り付けられ、この異物捕獲部材によ
つて燃料集合体への異物の流れが防止されて燃料
棒の健全性を維持することができ、その結果、原
子炉の安全性を向上させることができる効果を奏
する。
"Effects of the Invention" As described above, according to the central fuel support fitting according to the present invention, a net-like foreign matter capturing member is attached to the upstream side of the orifice, and this foreign matter capturing member prevents foreign matter from entering the fuel assembly. flow is prevented, the integrity of the fuel rods can be maintained, and as a result, the safety of the nuclear reactor can be improved.

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

第1図は本発明の係る中心部燃料支持金具の一
実施例を斜視図、第2図は第1図の断面図、第3
図は炉心構造を示す斜視図、第4図は燃料集合体
を示す部分断面図、第5図は従来例を示す斜視図
である。 27……中心部燃料支持金具、29……燃料集
合体、30……オリフイス、33……異物捕獲部
材。
FIG. 1 is a perspective view of an embodiment of the central fuel support fitting according to the present invention, FIG. 2 is a sectional view of FIG. 1, and FIG.
The figure is a perspective view showing the core structure, FIG. 4 is a partial sectional view showing a fuel assembly, and FIG. 5 is a perspective view showing a conventional example. 27... Center fuel support fitting, 29... Fuel assembly, 30... Orifice, 33... Foreign matter capturing member.

Claims (1)

【特許請求の範囲】 1 沸騰水型原子炉の炉心支持板の中心側に配置
され、複数の燃料集合体の下端部を支持する中心
部燃料支持金具であつて、その下側から燃料集合
体にわたつて冷却材流路が形成されたものにおい
て、 前記冷却材流路の入口部にオリフイスを有し、
そのオリフイスの上流側に網状の異物捕獲部材を
取り付けたことを特徴とする中心部燃料支持金
具。
[Scope of Claims] 1. A central fuel support fitting that is disposed on the center side of a core support plate of a boiling water reactor and supports the lower end portions of a plurality of fuel assemblies, and that supports the fuel assemblies from below. A coolant flow path is formed in the coolant flow path, and an orifice is provided at the entrance of the coolant flow path;
A central fuel support fitting characterized in that a net-like foreign matter capturing member is attached to the upstream side of the orifice.
JP62194507A 1987-08-05 1987-08-05 Support metal fitting of center part Granted JPS6438691A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP62194507A JPS6438691A (en) 1987-08-05 1987-08-05 Support metal fitting of center part

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP62194507A JPS6438691A (en) 1987-08-05 1987-08-05 Support metal fitting of center part

Publications (2)

Publication Number Publication Date
JPS6438691A JPS6438691A (en) 1989-02-08
JPH057679B2 true JPH057679B2 (en) 1993-01-29

Family

ID=16325674

Family Applications (1)

Application Number Title Priority Date Filing Date
JP62194507A Granted JPS6438691A (en) 1987-08-05 1987-08-05 Support metal fitting of center part

Country Status (1)

Country Link
JP (1) JPS6438691A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0924923A (en) * 1995-07-07 1997-01-28 Katsumi Yoshida Packaging container made of synthetic resin sheet

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS61284696A (en) * 1985-06-12 1986-12-15 株式会社日立製作所 Fuel support metal and nuclear reactor
JPS6296891A (en) * 1985-10-24 1987-05-06 株式会社東芝 Fuel aggregate

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS61284696A (en) * 1985-06-12 1986-12-15 株式会社日立製作所 Fuel support metal and nuclear reactor
JPS6296891A (en) * 1985-10-24 1987-05-06 株式会社東芝 Fuel aggregate

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0924923A (en) * 1995-07-07 1997-01-28 Katsumi Yoshida Packaging container made of synthetic resin sheet

Also Published As

Publication number Publication date
JPS6438691A (en) 1989-02-08

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