JPH06138271A - Fuel assembly for boiling water reactor - Google Patents

Fuel assembly for boiling water reactor

Info

Publication number
JPH06138271A
JPH06138271A JP4051070A JP5107092A JPH06138271A JP H06138271 A JPH06138271 A JP H06138271A JP 4051070 A JP4051070 A JP 4051070A JP 5107092 A JP5107092 A JP 5107092A JP H06138271 A JPH06138271 A JP H06138271A
Authority
JP
Japan
Prior art keywords
wall surface
water channel
fuel
fuel assembly
channel
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
JP4051070A
Other languages
Japanese (ja)
Inventor
Toru Izumitani
徹 泉谷
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.)
Nuclear Fuel Industries Ltd
Original Assignee
Nuclear Fuel 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 Nuclear Fuel Industries Ltd filed Critical Nuclear Fuel Industries Ltd
Priority to JP4051070A priority Critical patent/JPH06138271A/en
Publication of JPH06138271A publication Critical patent/JPH06138271A/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

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

PURPOSE:To operate a reactor core of enhanced fuel output and to prevent creep deformation of a water channel wall due to the difference between inner and outer pressures CONSTITUTION:Flow trippers 2 are mounted at proper intervals to the overall length of the wall surface of a rectangular water channel 1 provided within a fuel assembly 10. A coolant flowing on the wall surface of the channel is deviated toward a fuel rod 11 adjoining to the wall surface of the channel by the flow trippers 2 serving as protruding portions, so as to enhance the cooling efficiency of the fuel rod and to enable the operation of a reactor to enhance the fuel output and to reduce the flow rate of coolant Also, creep deformation due to the difference between inner and outer pressures can be prevented by increasing the strength of the wall surface of the channel.

Description

【発明の詳細な説明】Detailed Description of the Invention

【0001】[0001]

【産業上の利用分野】本発明は、沸騰水型原子炉(以下
BWRと略す)用燃料集合体のウォーターチャンネルの
壁面に冷却材のフロートリッパ(流れ転向手段)として
突起物が設けられているBWR用燃料集合体に関するも
のである。
BACKGROUND OF THE INVENTION 1. Field of the Invention In the present invention, a projection is provided as a coolant flow tripper (flow turning means) on a wall surface of a water channel of a fuel assembly for a boiling water reactor (hereinafter abbreviated as BWR). The present invention relates to a BWR fuel assembly.

【0002】[0002]

【従来の技術】BWR用燃料集合体において、従来はそ
の中央部分の燃料棒を1〜2本欠如してその代りに燃料
棒とほぼ同一外径のウォーターロッドを装荷し、このウ
ォーターロッド内を冷却材が通過するようにして、冷却
材による中性子減速効果を高めるとともに、周辺部の燃
料棒については、核燃料の濃縮度を低くし、さらに中央
部の燃料棒については、核燃料の濃縮度を高くして、水
平方向の出力分布の均一化を図るようにしていた。しか
しながら、従来のウォーターロッドでは細径であったた
め、出力分布の均一化が十分に図れず、核燃料の濃縮度
を周辺部と中央部とで差を設定しなければならないとい
う複雑さがあった。そこで、一辺の長さが燃料棒直径の
約3.5倍、収容面積が燃料棒のほぼ9本分に相当する
角型のウォーターチャンネルを中央部分に置き、出力分
布の均一化および中性子の減速効果を向上させる図5に
示すBWR用燃料集合体が提案されている。同図におい
て、1はウォーターチャンネル,10は燃料集合体,1
1は燃料棒,12はスペーサ,13は上部タイプレー
ト,14は下部タイプレートである。さらに燃料の高燃
焼度化に伴い、燃料出力を高めるとともに、冷却材流量
を減らした運転など、原子炉運転のフレキシビリティの
向上が要求されている。また、角型ウォーターチャンネ
ルを用いた構造では、冷却材の炉内滞在期間が長くなる
と、内外圧差によるクリープ変形等が起こりやすくな
り、ウォーターチャンネルの壁面が外側へ膨出して、ス
ペーサとの係合上好ましくなく、これらを防ぐ手段が要
求されている。この変形はウォーターチャンネルの中央
部より、上,下部で大きくなることが知られている。
2. Description of the Related Art In a BWR fuel assembly, conventionally, one or two fuel rods in the central portion thereof are omitted, and instead, a water rod having substantially the same outer diameter as that of the fuel rod is loaded, and the inside of this water rod is loaded. By allowing the coolant to pass through, the neutron moderating effect of the coolant is enhanced, the nuclear fuel enrichment is reduced in the peripheral fuel rods, and the nuclear fuel enrichment is increased in the central fuel rods. Then, the output distribution in the horizontal direction is made uniform. However, since the conventional water rod has a small diameter, the output distribution cannot be sufficiently made uniform, and there is a complexity in that a difference in the enrichment of the nuclear fuel must be set between the peripheral portion and the central portion. Therefore, a square water channel with a side length of about 3.5 times the fuel rod diameter and a storage area equivalent to about 9 fuel rods was placed in the center to make the power distribution uniform and slow down neutrons. A fuel assembly for BWR shown in FIG. 5 that improves the effect has been proposed. In the figure, 1 is a water channel, 10 is a fuel assembly, 1
1 is a fuel rod, 12 is a spacer, 13 is an upper tie plate, and 14 is a lower tie plate. Further, as the burnup of fuel becomes higher, it is required to increase the fuel output and to improve the flexibility of the reactor operation such as the operation in which the flow rate of the coolant is reduced. In addition, in the structure using square water channels, when the coolant stays in the furnace for a long time, creep deformation due to the pressure difference between the inside and outside tends to occur, and the wall surface of the water channel bulges outward and engages with the spacer. This is not preferable, and means for preventing these are required. It is known that this deformation is larger in the upper and lower parts than in the central part of the water channel.

【0003】[0003]

【発明が解決しようとする課題】本発明は、BWR用燃
料集合体のウォーターチャンネル壁面上を流れる冷却材
をウォーターチヤンネル壁に隣接する燃料棒の方へそら
して燃料棒の冷却効率を高め、燃料の出力を高めた運
転、または冷却材流量を減らした運転を可能とし、さら
にウォーターチャンネルの強度を向上させ、内外圧差に
よるクリープ変形等を防ぐことを目的とするものであ
る。
SUMMARY OF THE INVENTION According to the present invention, the coolant flowing on the water channel wall surface of the fuel assembly for BWR is diverted toward the fuel rod adjacent to the water channel wall to improve the cooling efficiency of the fuel rod. It is an object of the present invention to enable the operation of increasing the output of or the operation of decreasing the flow rate of the coolant, further improve the strength of the water channel, and prevent the creep deformation and the like due to the difference in internal and external pressures.

【0004】[0004]

【課題を解決するための手段】本発明は上記の目的を達
成するためになされたもので、燃料集合体内に設けた角
型のウォーターチャンネルの壁面の全長にわたって適当
な間隔をあけて、突起部すなわちフロートリッパを取り
付けることにした。またその形状は下部タイプレートの
方から上部タイプレートの方へ高さを増し、その傾斜部
はウォーターチャンネルの中心寄りにやや湾曲している
ものである。
SUMMARY OF THE INVENTION The present invention has been made to achieve the above object, and the protrusions are formed at appropriate intervals over the entire length of the wall surface of the rectangular water channel provided in the fuel assembly. That is, I decided to attach a flow tripper. Moreover, the shape increases in height from the lower tie plate toward the upper tie plate, and the inclined portion is slightly curved toward the center of the water channel.

【0005】[0005]

【作用】角型ウォーターチャンネルにフロートリッパを
取り付けることにより、非発熱体であるウォーターチャ
ンネルの壁面上を流れる冷却材をウォーターチャンネル
壁面に隣接する燃料棒の方へそらして、燃料棒の冷却効
率を高め、燃料の出力を高めた運転、または冷却材流量
を減らした運転を可能とし、さらにウォーターチャンネ
ル壁面の強度を向上させて内外圧差によるクリープ変形
等を防ぐことができる。
By attaching the flow tripper to the square water channel, the coolant flowing on the wall surface of the water channel, which is a non-heating element, is diverted toward the fuel rod adjacent to the wall surface of the water channel to improve the cooling efficiency of the fuel rod. It is possible to increase the fuel output and increase the fuel output, or to reduce the coolant flow rate, and further improve the strength of the wall surface of the water channel to prevent creep deformation and the like due to the internal / external pressure difference.

【0006】[0006]

【実施例】図1は本発明のBWR用燃料集合体の簡略要
部説明図で、ウォーターチャンネル1の壁面に適当な間
隔でフロートリッパ2を取り付けたものである。
DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS FIG. 1 is a simplified schematic view of a BWR fuel assembly according to the present invention, in which a flow tripper 2 is attached to a wall surface of a water channel 1 at appropriate intervals.

【0007】図2〜図4はそれぞれ本発明に係るBWR
用燃料集合体のウォーターチャンネル壁面に取り付けら
れているフロートリッパの形状とその取付け方法の説明
図である。図2の実施例は溶接によって取り付ける場合
のフロートリッパの形状を示すもので、2aは上面図,
2bは正面図,2cは側面図である。この場合、フロー
トリッパの材質は溶接性のため、チャンネルボックスと
同材質、すなわちジルカロイ4が望ましい。図3の実施
例は、フロートリッパをウォーターチャンネルの壁面の
削り出しによって設けたものの縦断面説明図で、1はウ
ォーターチャンネル,2はフロートリッパである。図4
の実施例は、フロートリッパをウォーターチャンネルの
壁面に打ち出しによって設けたものの縦断面図で、、1
はウォーターチャンネル,2はフロートリッパである。
2 to 4 are BWRs according to the present invention.
It is explanatory drawing of the shape of the flow tripper attached to the water channel wall surface of the fuel assembly for vehicles, and its attachment method. The embodiment of FIG. 2 shows the shape of the flow tripper when attached by welding. 2a is a top view,
2b is a front view and 2c is a side view. In this case, since the material of the flow tripper is weldable, the same material as the channel box, that is, Zircaloy 4 is desirable. In the embodiment of FIG. 3, a flow tripper is provided by cutting out the wall surface of a water channel, and FIG. 3 is a vertical cross-sectional explanatory view, in which 1 is a water channel and 2 is a flow tripper. Figure 4
The embodiment of FIG. 1 is a longitudinal sectional view of a flow tripper provided by stamping on the wall surface of a water channel.
Is a water channel, and 2 is a flow tripper.

【0008】[0008]

【発明の効果】本発明による効果はフロートリッパを取
り付けることにより、 (1)燃料の出力を高めた原子炉の運転 (2)ウォーターチャンネル壁の内外圧差によるクリー
プ変形の防止 の2点が可能となる。
EFFECTS OF THE INVENTION The effects of the present invention can be achieved by installing a flow tripper, (1) operation of a reactor with increased fuel output, and (2) prevention of creep deformation due to pressure difference between inside and outside of water channel wall. Become.

【図面の簡単な説明】[Brief description of drawings]

【図1】BWR用燃料集合体のウォーターチャンネルの
壁面にフロートリッパを取り付けた実施例説明図であ
る。
FIG. 1 is an explanatory view of an embodiment in which a flow tripper is attached to a wall surface of a water channel of a BWR fuel assembly.

【図2】溶接によりウォーターチャンネルの壁面に取り
付けるフロートリッパの形状の実施例説明図である。
FIG. 2 is an explanatory view of an embodiment of the shape of a flow tripper attached to the wall surface of a water channel by welding.

【図3】ウォーターチャンネル壁面の削り出しによるフ
ロートリッパの実施例の形状断面図である。
FIG. 3 is a sectional view of the shape of an embodiment of a flow tripper by carving out the wall surface of a water channel.

【図4】ウォーターチャンネル壁面の打ち出しによるフ
ロートリッパの実施例の形状断面図である。
FIG. 4 is a sectional view of the shape of an embodiment of a flow tripper by punching a wall surface of a water channel.

【図5】従来のBWR用燃料集合体の簡略断面説明図で
ある。
FIG. 5 is a schematic cross-sectional explanatory view of a conventional BWR fuel assembly.

【符号の説明】[Explanation of symbols]

1 ウォーターチャンネル 2 フロートリッパ 2a 溶接によるフロートリッパの上面図 2b 溶接によるフロートリッパの正面図 2c 溶接によるフロートリッパの側面図 10 燃料集合体 11 燃料棒 12 スペーサ 13 上部タイプレート 14 下部タイプレート 1 Water Channel 2 Flow Tripper 2a Top View of Flow Tripper by Welding 2b Front View of Flow Tripper by Welding 2c Side View of Flow Tripper by Welding 10 Fuel Assembly 11 Fuel Rods 12 Spacer 13 Upper Tie Plate 14 Lower Tie Plate

Claims (1)

【特許請求の範囲】[Claims] 【請求項1】 沸騰水型原子炉用燃料集合体内中央部に
位置するウォーターチャンネルに、形状が下部タイプレ
ートの方から上部タイプレートの方へ高さを増し、その
傾斜部はウォーターチャンネルの中心よりにやや湾曲し
ているフロートリッパが複数個壁面に取り付けられてい
ることを特徴とする沸騰水型原子炉用燃料集合体。
1. A water channel located in the central portion of a fuel assembly for a boiling water reactor, the shape of which increases from the lower tie plate toward the upper tie plate, and the sloped portion is the center of the water channel. A fuel assembly for a boiling water reactor, comprising a plurality of slightly curved flow trippers attached to a wall surface.
JP4051070A 1992-01-24 1992-01-24 Fuel assembly for boiling water reactor Pending JPH06138271A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP4051070A JPH06138271A (en) 1992-01-24 1992-01-24 Fuel assembly for boiling water reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP4051070A JPH06138271A (en) 1992-01-24 1992-01-24 Fuel assembly for boiling water reactor

Publications (1)

Publication Number Publication Date
JPH06138271A true JPH06138271A (en) 1994-05-20

Family

ID=12876548

Family Applications (1)

Application Number Title Priority Date Filing Date
JP4051070A Pending JPH06138271A (en) 1992-01-24 1992-01-24 Fuel assembly for boiling water reactor

Country Status (1)

Country Link
JP (1) JPH06138271A (en)

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Legal Events

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Effective date: 20000704