JPS5985989A - Method of processing baffle joint of pwr type reactor - Google Patents

Method of processing baffle joint of pwr type reactor

Info

Publication number
JPS5985989A
JPS5985989A JP57195768A JP19576882A JPS5985989A JP S5985989 A JPS5985989 A JP S5985989A JP 57195768 A JP57195768 A JP 57195768A JP 19576882 A JP19576882 A JP 19576882A JP S5985989 A JPS5985989 A JP S5985989A
Authority
JP
Japan
Prior art keywords
flow velocity
flow
gap
baffle
baffle plate
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
JP57195768A
Other languages
Japanese (ja)
Inventor
益子 裕之
柳瀬 潤章
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 JP57195768A priority Critical patent/JPS5985989A/en
Publication of JPS5985989A publication Critical patent/JPS5985989A/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

  • Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (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】 〔技術分野〕 加圧水型原子炉では、バッフル板の隙間がら、噴流(パ
ンフル流)が吹き込み、核燃料棒を振動サセ、場合ニJ
:っては、核燃料棒を破損させるこがある。本発明はこ
の振動を防止するため、バッフル板の継ぎ目を加工する
方法に関するものである。
[Detailed Description of the Invention] [Technical Field] In a pressurized water nuclear reactor, a jet stream (panfur stream) blows through the gap between the baffle plates, vibrates the nuclear fuel rods, and in some cases
: This can damage nuclear fuel rods. The present invention relates to a method of processing the joints of baffle plates in order to prevent this vibration.

〔従来技術と問題点〕[Conventional technology and problems]

従来は第1図(イ)に示すようにバッフル板1.1’の
継ぎ目に生じる隙間2は(ロ)のようにピーニングによ
り、ギャップを狭くしてその解決企図っている。3はピ
ーニングによって狭くなったギャップである。なお、(
切では隙間2を拡大して示している。しかし、この方法
ではギャップを完全にふさぐことは不可能で、しかも先
端部を狭くしているため流速はむ・しろ大きくなってし
まうことがある。
Conventionally, as shown in FIG. 1(A), the gap 2 occurring at the joint between the baffle plates 1.1' has been solved by narrowing the gap by peening as shown in FIG. 1(B). 3 is a gap narrowed by peening. In addition,(
Gap 2 is shown enlarged in the illustration. However, with this method, it is impossible to completely close the gap, and since the tip is narrowed, the flow velocity may even increase.

また、バッフル板は原子炉運転中、高温になるため熱膨
張を起し、いったんピーニングしたギャップが再び広が
り、核燃料棒を過度に振動させる程度の流速になること
もある。
Furthermore, during reactor operation, baffle plates reach high temperatures and undergo thermal expansion, which can cause gaps that have been peened to widen again, resulting in flow velocities that can cause the nuclear fuel rods to vibrate excessively.

〔発明の構成と実施例〕[Structure and embodiments of the invention]

まず、スリットから噴出する流れについて説明する。 First, the flow ejected from the slit will be explained.

狭いスリットから1出する流れは次式で表される。第2
図においてd、をスリット幅、 U、をスリット出口流
速、u、をセンターライン流速、UをfLt点における
流速+ x+ Yを坐標、Cを常数とすると、 但し C=θ109 (参考文献 耗り、 AlbertsOn 、 Y、 
B、 Dai et al。
The flow coming out of a narrow slit is expressed by the following equation. Second
In the figure, d is the slit width, U is the flow velocity at the slit exit, u is the centerline flow velocity, U is the flow velocity at the fLt point + x + Y is the seat mark, and C is a constant. AlbertsOn, Y.
B. Dai et al.

Diffusion of subFnerged J
ets(Proc、of ASCE vol  7IL
t Dec  /ワll了)このことから、スリット幅
の約5倍の距離までは、噴流の幅が広がっていないこと
を示している。これはL D V(La5er Dop
pler Velocimeter )を用いて確めら
れた。
Diffusion of subFenerged J
ets(Proc, of ASCE vol 7IL
This shows that the width of the jet does not expand up to a distance that is approximately five times the slit width. This is LDV(La5er Dop)
Pler Velocimeter).

即ち、第3図(イ)はセンターライン流速、(嗜は流速
分布を示−し、かつ矢印の長さは流速の大きさで実測値
である。
That is, FIG. 3(a) shows the centerline flow velocity, (indicates the flow velocity distribution, and the length of the arrow indicates the actual measured value of the flow velocity.

次に噴出孔が広くなった時の流れについて第4図に基づ
いて説明する。
Next, the flow when the ejection hole becomes wider will be explained based on FIG. 4.

噴出口を広くすると、水は壁に沿って流れるようになる
。前述のことから広げる奥行をスリット幅d。の約5倍
以上とれば噴流の幅が広がる。噴流では運動量保存則に
より の関係かあるので、噴流の幅が広がれば流速Uは遅くな
る。また、上式に示すように、噴流の噴流分布はy/x
に対し相似凱を満たす。従っである点で噴流の幅がn倍
になれば、その点の流速は庖になる。
By widening the spout, water will flow along the wall. From the above, the depth to be expanded is the slit width d. If it is about 5 times or more, the width of the jet will increase. In a jet flow, there is a relationship based on the law of conservation of momentum, so as the width of the jet widens, the flow velocity U becomes slower. Also, as shown in the above equation, the jet distribution of the jet is y/x
Satisfies Gai similar to. Therefore, if the width of the jet stream increases by n times at a certain point, the flow velocity at that point will increase.

本発明は上記の点に鑑みなされたもので、バッフル板の
継ぎ目を炉心側から広げて加工することを特徴とする加
圧水型原子炉のバッフル板の継ぎ回加工法である。
The present invention has been made in view of the above points, and is a method for joint processing of baffle plates for a pressurized water reactor, which is characterized in that the joints of the baffle plates are widened from the core side.

バッフル板間の隙間は、最大07〜0,3關程度、その
部分の流速は70〜20m/Sと推定される。核燃料棒
の振動には、発振限界の流速があり、それ以下であれば
振動は起らない。パンフル板隙間の原子炉側継ぎ目表面
を第5図のように斜線部分4゜4り削って広げ、バッフ
ル流を乱すことにより、パンフル流速を発振限界流速以
下に下げる。この広げた部分には炉心下方から一次冷却
水が流れ込むため、バッフル流は十分に乱される。また
、さらにバッフル流速を遅くするために、継ぎ目を広げ
ることによって生じL2部分に円柱5等(多角形俸でも
よい)を両側に第6図(イ)、、−(コ)のように交互
に溶接6すれば効果を一層増すことができる。なお(ロ
)は(イ)を矢印a方向から見た図である。
The gap between the baffle plates is estimated to be about 0.7 to 0.3 degrees at maximum, and the flow velocity in that area is estimated to be 70 to 20 m/s. There is an oscillation limit flow velocity for the vibration of nuclear fuel rods, and if the flow velocity is below that, vibrations will not occur. As shown in Figure 5, the surface of the reactor-side seam between the panfuru plates is widened by shaving 4 degrees of the shaded area to disturb the baffle flow, thereby reducing the panfuru flow velocity below the oscillation limit flow velocity. Because primary cooling water flows into this expanded portion from below the core, the baffle flow is sufficiently disturbed. In addition, in order to further slow down the baffle flow velocity, cylinders 5, etc. (polygonal shapes may be used) are placed on both sides of the L2 part created by widening the seam, alternately as shown in Figure 6 (A), - (C). Welding 6 can further increase the effect. Note that (b) is a diagram of (a) viewed from the direction of arrow a.

なお、第6図の円柱または多角形俸はステンレスで作成
し、両側の板に溶接して、熱膨張による変位に耐え、十
分な強度をもつように取りつ□ける。
The cylindrical or polygonal bale shown in Fig. 6 is made of stainless steel and welded to the plates on both sides so that it can withstand displacement due to thermal expansion and has sufficient strength.

原子炉で燃料棒を振動させていると考えられる流速はン
O〜、lQ m / Sであるが、噴流の流速を′・ろ
−にすれば燃料棒の振動は発生しないと考えられる。
The flow velocity that is thought to vibrate the fuel rods in a nuclear reactor is 1Q m/S, but it is thought that if the flow velocity of the jet stream is set to 0.0, the fuel rods will not vibrate.

従って加工する寸法としては第7図に示すように、九≦
θjam、、も=ハ・、 ノ、=t・毒 が好ましい。
Therefore, as shown in Figure 7, the dimensions to be processed are 9≦
θjam,,mo=ha・,ノ,=t・poison are preferable.

〔効果〕 − 従来のバッフル対策であるピーニングでは、バッフル板
の隙間を完全にふさぐことは不可能であり、表面の部分
のみを狭くするだけにとソまり、むしろバッフル流速の
増大を伴う危険性が大きかった。
[Effect] - With peening, which is a conventional baffle countermeasure, it is impossible to completely close the gap between the baffle plates, and it only narrows the surface area, which may actually increase the baffle flow velocity. was big.

本発明では、パンフル板の隙間表面部を拡大することに
より、炉内の一次冷却水の流れとの相互作用により燃料
棒に対して横方向に作用するバッフル流が乱されて流速
が減少するため、燃料棒に作用する力が激減し、燃料棒
の過度の振動を防止することができるのが大きな効果で
ある。
In the present invention, by enlarging the surface area of the gap between the baffle plates, the baffle flow that acts transversely to the fuel rods is disturbed due to interaction with the flow of primary cooling water in the reactor, and the flow velocity is reduced. A major effect is that the force acting on the fuel rods is drastically reduced and excessive vibration of the fuel rods can be prevented.

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

第11](イ)はバッフル板とその継ぎ目の隙間の説明
図、(→はピーニングによりギャップを小さくした説明
図、第2図は狭いスリットから噴出する流れの説明図、
第3図はLDVによる流速の特性図で、(イ)はセンタ
ーライン流速、(ロ)は流速分布の説明図、第4図は噴
出孔が広くなった時の流れについての説明図、第5図は
バッフル板の継ぎ目を炉心側より広げる説明図、第6図
は第5図により広げた隙間に円柱等を設けてバッフル板
に溶接する説明図、第7図は本発明による広げた隙間の
サイズを示す説明図である。 i、1′・・・バッフル板、2・・・バッフル板継キ目
の隙間、3・・・ピーニングにより狭くなった部分、4
゜4′・・・継ぎ目の隙間を広げるために削り取る部分
、5・・・円柱、6・・・溶接、d、・・・スリット幅
、U、・・・スリット出口流速、u、・・・センターラ
イン流速、U・・・任意のライン上の流速、L(x)・
・・Xの位置での流れの幅のA 7r1図 (イ)                      
   (ロ)12図 雪4図
11] (a) is an explanatory diagram of the gap between the baffle plate and its joint, (→ is an explanatory diagram of the gap reduced by peening, and Fig. 2 is an explanatory diagram of the flow ejecting from a narrow slit,
Figure 3 is a characteristic diagram of the flow velocity by LDV, (a) is the centerline flow velocity, (b) is an explanatory diagram of the flow velocity distribution, Figure 4 is an explanatory diagram of the flow when the nozzle becomes wider, and The figure is an explanatory diagram of expanding the seam of the baffle plate from the core side, Figure 6 is an explanatory diagram of installing a cylinder etc. in the gap widened as shown in Figure 5 and welding it to the baffle plate, and Figure 7 is an explanatory diagram of the widened gap according to the present invention. It is an explanatory view showing size. i, 1'...Baffle plate, 2...Gap between baffle plate joints, 3...Narrowed part due to peening, 4
゜4'... Part to be scraped to widen the gap between joints, 5... Cylinder, 6... Welding, d,... Slit width, U,... Slit exit flow velocity, u,... Center line flow velocity, U...Flow velocity on any line, L(x).
・・Flow width at position X A 7r1 diagram (a)
(b) Figure 12 Snow Figure 4

Claims (1)

【特許請求の範囲】 1、 炉心側よりバッフル板の継ぎ目を広げることを特
徴とする加圧木型原子炉バッフル板継ぎ目の加工法。 2、−次冷却水およびバッフル流の流速を乱す円柱等の
物体を炉心下方からバッフル板継ぎ目に沿って設けるこ
とを特徴とする特許請求の範囲第1項記載の加圧水型原
子炉バッフル板継ぎ目の加工法。
[Claims] 1. A method for processing baffle plate joints in a pressurized wooden nuclear reactor, which is characterized by widening the baffle plate joints from the core side. 2. Pressurized water reactor baffle plate joint according to claim 1, characterized in that an object such as a cylinder that disturbs the flow velocity of the secondary cooling water and the baffle flow is provided along the baffle plate joint from below the core. Processing method.
JP57195768A 1982-11-08 1982-11-08 Method of processing baffle joint of pwr type reactor Pending JPS5985989A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57195768A JPS5985989A (en) 1982-11-08 1982-11-08 Method of processing baffle joint of pwr type reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57195768A JPS5985989A (en) 1982-11-08 1982-11-08 Method of processing baffle joint of pwr type reactor

Publications (1)

Publication Number Publication Date
JPS5985989A true JPS5985989A (en) 1984-05-18

Family

ID=16346632

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57195768A Pending JPS5985989A (en) 1982-11-08 1982-11-08 Method of processing baffle joint of pwr type reactor

Country Status (1)

Country Link
JP (1) JPS5985989A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2014088872A (en) * 2012-08-27 2014-05-15 General Electric Co <Ge> Components with cooling channels and manufacturing methods

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2014088872A (en) * 2012-08-27 2014-05-15 General Electric Co <Ge> Components with cooling channels and manufacturing methods

Similar Documents

Publication Publication Date Title
JP3689114B2 (en) Combustor liner equipment
Wu et al. Understanding of humping formation and suppression mechanisms using the numerical simulation
JPS60168554A (en) Jet nozzle in liquid
Tiwari et al. Numerical prediction of flow and heat transfer in a channel in the presence of a built-in circular tube with and without an integral wake splitter
Wang et al. Impact of cooling injection on the transonic over-tip leakage flow and squealer aerothermal design optimization
Gilard et al. Slot jet impinging on a concave curved wall
JPS5985989A (en) Method of processing baffle joint of pwr type reactor
Luo et al. Numerical analysis for film cooling characteristics of trenched hole under the effects of rib-disturbed feed flow and curved surface
JP4982846B2 (en) Equipment for reducing pressure fluctuations in supersonic cavities
Ligrani et al. Flow phenomena in swirl chambers
EP0020375A1 (en) Heat exchanger having inclined tubes.
JP2006110620A (en) Continuous casting method
EP0253479B1 (en) Modification of the rate of heat or mass transfer in a stream of liquid metal
Toyoda et al. Visualization of the vortical structure of a circular jet excited by axial and azimuthal perturbations
JP3241241B2 (en) Hollow gas turbine blades
JPH03185394A (en) Fuel assembly with liquid film peeling device for boiling water type nuclear reactor
JP2592508B2 (en) Bending suction pipe turning suppression fin
JP2000046485A (en) Heat transporting system
Sekoguchi et al. Experimental investigation of the alternate dry and rewet (ADR) on heated tubes with and without an obstruction in flow boiling
Maruthupandiyan et al. Tab location effect on supersonic jet mixing
MASUDA et al. An experimental study on an underexpanded annular impinging jet
JPS6344699Y2 (en)
JPS6014498A (en) Forcible air cooling heat sink unit
JPS607390A (en) Aggregate of nuclear fuel
Lee et al. Flow characteristics of a 35 inclined turbulent jet in a crossflow on a concave surface