JPS6088389A - Recirculating piping system of boiling-water type nuclear power plant - Google Patents

Recirculating piping system of boiling-water type nuclear power plant

Info

Publication number
JPS6088389A
JPS6088389A JP58196601A JP19660183A JPS6088389A JP S6088389 A JPS6088389 A JP S6088389A JP 58196601 A JP58196601 A JP 58196601A JP 19660183 A JP19660183 A JP 19660183A JP S6088389 A JPS6088389 A JP S6088389A
Authority
JP
Japan
Prior art keywords
cross
piping system
branch
flow
pipe
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
JP58196601A
Other languages
Japanese (ja)
Inventor
渉 佐川
吉永 洋一
正 水野
三浦 誠二
小谷 皓市
小玉 郁夫
根目沢 勲
泉山 昭政
公一 鈴木
小杉 伸夫
武原 秀俊
敬 伊東
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.)
Hitachi Ltd
Original Assignee
Hitachi 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 Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP58196601A priority Critical patent/JPS6088389A/en
Publication of JPS6088389A publication Critical patent/JPS6088389A/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
    • 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

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Heat Treatment Of Water, Waste Water Or Sewage (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】 本発明は原子力プラントの配管系に係り、特に、沸騰水
型原子炉において炉心に供給する冷却材流量の調整を行
なう系統であるPLR系の配管系に関するものである。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a piping system for a nuclear power plant, and particularly to a piping system for a PLR system, which is a system for adjusting the flow rate of coolant supplied to a reactor core in a boiling water nuclear reactor.

従来技術によるPLR系配管を、第1図に示す、1は、
原子炉圧力容器を示す。以下、原子炉圧力容器1に取付
られる再循環系配管は、次のような構成となつている。
The PLR system piping according to the prior art is shown in FIG.
The reactor pressure vessel is shown. The recirculation system piping attached to the reactor pressure vessel 1 has the following configuration.

曲管部20、テイー付直管部21、入口弁5、原子炉圧
力容器1内に水を強制循環させるためのポンプ7、ポン
プ7を駆動するためのモーター8、出口弁9、母管22
、十字分岐管(以下クロスと呼ぶ)11、ヘツダ曲管1
2、レジユーサ13、ライザー管24、の各配管部品を
それぞれ突合わせ溶接により第1図に示すように構成さ
れている。
Bent pipe section 20, straight pipe section 21 with tee, inlet valve 5, pump 7 for forced circulation of water in reactor pressure vessel 1, motor 8 for driving pump 7, outlet valve 9, main pipe 22
, cross branch pipe (hereinafter referred to as cross) 11, header bent pipe 1
2, the reducer 13, and the riser pipe 24 are constructed as shown in FIG. 1 by butt welding.

BWRプラントの運転時において、PLR系配管内を原
子炉圧力容器1内の冷却材が流れる。すなわち、ポンプ
7が駆動され、原子炉圧力容器1内の冷却材は、曲管部
20、テイー付直管部21、入口弁5、ポンプ7、バル
プ9、母管22を順次通過して、クロス11内に流入す
る。冷却材は、クロス11によつて流動系統が分けられ
、その一部はクロス11から、直接、レジユーサ13ラ
イガー管24を通して、原子炉圧力容器1内のジエツト
ポンプ(図示せず)内に噴出される。大部分である残り
の冷却材は、クロス11からヘツダ曲管12、ライザー
管24を経てジエツトポンプ内に吐出される。
During operation of the BWR plant, coolant in the reactor pressure vessel 1 flows through the PLR system piping. That is, the pump 7 is driven, and the coolant in the reactor pressure vessel 1 sequentially passes through the bent pipe section 20, the straight pipe section with tee 21, the inlet valve 5, the pump 7, the valve 9, and the main pipe 22. It flows into the cross 11. The flow system of the coolant is divided by the cross 11, and a part of the coolant is directly injected from the cross 11 through the reducer 13 and the liger pipe 24 into a jet pump (not shown) in the reactor pressure vessel 1. . The remaining coolant, which is the majority, is discharged from the cross 11 through the header bend pipe 12 and the riser pipe 24 into the jet pump.

第2、3図にクロス部の詳細を示す。Figures 2 and 3 show details of the cross section.

母管からの流れf0は十字分岐部で、ヘツダー曲管方向
への流れf1、f2、レジユーサ方向への流れf3の分
岐流れとなる。
The flow f0 from the main pipe becomes a branched flow at a cross branching point, into flows f1 and f2 in the header curved pipe direction and a flow f3 in the reservoir direction.

上記十字管部の流れは、第4図、第5図に示すように、
渦芯が、両側のヘツダ曲管に貫通するような流れ(第4
図)と、中央に渦がなくレジユーサ部13付近で非常に
不規則な流動を呈する、流体力学的に不安定流れとがあ
り、その流れが交互に繰り返す。すなわち、十字管部の
流れは渦の発生消滅があつて配管内の流動が不安定にな
り、分岐部における各方向への流動抵抗等が変動し、そ
れに従い、各ライザー管への流量配分や圧力損失が時間
的に変動することになり、それがBWRプラントの出力
変動につながる可能性がある。
The flow in the cross pipe section is as shown in Figures 4 and 5.
A flow in which the vortex core penetrates the header curved pipes on both sides (fourth
(Fig.) and a hydrodynamically unstable flow that has no vortex in the center and exhibits a very irregular flow near the reducer portion 13, and these flows alternately repeat. In other words, in the flow in the cross pipe section, vortices occur and disappear, making the flow in the pipe unstable, and the flow resistance in each direction at the branch section fluctuates, and accordingly, the flow rate distribution to each riser pipe or The pressure drop will vary over time, which may lead to variations in the output of the BWR plant.

(目的) 本発明の目的は、前記した従来技術の欠点をなくし、安
定な運転の原子力プラントを提供するにある。
(Objective) The object of the present invention is to eliminate the drawbacks of the prior art described above and to provide a nuclear power plant with stable operation.

(要点) 本発明の特徴は、母管とヘツダー曲り管及びライザー管
の交差部である十字分岐管の内部に、渦が発生したり、
消滅したりして流れを不安定にしている点に着目し、こ
の不安定な流動を解消する手段として、十字管内部を常
に流れを流体力学的安定状態に保つ構造とした点にある
。本発明は可視化実験によつて十字管部の流動状況を検
討した結果なされたものである。
(Key Points) A feature of the present invention is that a vortex is generated inside the cross-branch pipe, which is the intersection of the main pipe, the header bend pipe, and the riser pipe.
We focused on the fact that the flow becomes unstable due to the disappearance of water, and as a means to eliminate this unstable flow, we designed the inside of the cross tube to have a structure that always maintains the flow in a hydrodynamically stable state. The present invention was developed as a result of examining the flow situation in the cross tube through visualization experiments.

(実施例とその効果) 以下、本発明の一実施例を第6図を参照して説明する。(Examples and their effects) Hereinafter, one embodiment of the present invention will be described with reference to FIG.

第6図は本発明による好適な一実施例であるPLR系配
管十字管部をなくした全体図を示す。従来例第3図と同
一構成は同一符号で示す。
FIG. 6 shows an overall view of a preferred embodiment of the present invention, with the PLR system piping cross pipe section removed. Components that are the same as those in the conventional example shown in FIG. 3 are designated by the same reference numerals.

母管22と相対するクロス部をなくし、テイー31を有
した構造である。
This structure has a tee 31 without a cross section facing the main pipe 22.

本実施例は上記のように、テイー構造にしたので、レジ
ユーサ部での不規則な流動が発生しにくくなる。すなわ
ち、テイー字管によりPLR系配管の流量分配を安定に
保つことができる。その結果、テイ分岐部から各方向へ
の流動抵抗等は変動することがなく、各ライが管への流
量分配や圧力損失が一定となり、BWRの出力変動は、
抑制される。また、原子炉内の流動も安定化し、材料強
度面からも好ましい状況となる。
As described above, this embodiment has a Tee structure, so that irregular flow in the reducer part is less likely to occur. That is, the Tee-shaped tube can maintain stable flow distribution in the PLR system piping. As a result, the flow resistance in each direction from the Tee branch does not change, and the flow distribution and pressure loss from each lie to the pipe are constant, and the BWR output fluctuation is
suppressed. In addition, the flow inside the reactor is stabilized, which is a favorable situation from the viewpoint of material strength.

第7図は、十字分岐管をなくし、第6図のテイ31の下
方に更にテイ32を構成する全体図であり、本実施例の
場合にも上記と同様の効果が達成される。
FIG. 7 is an overall view in which the cross branch pipe is eliminated and a tee 32 is further constructed below the tee 31 in FIG. 6, and the same effects as described above are achieved in this embodiment as well.

尚、本実施例は、原子炉圧力容器1とPLR配管系との
取合を現有国内プラントと同一にする場合である。
In this embodiment, the arrangement of the reactor pressure vessel 1 and the PLR piping system is the same as that of an existing domestic plant.

第8図は、従来構造のレジユーサ部での不規則な流動を
ヘツダー曲管12に与えないようレジユーサ13の位置
を上げ(母管22と対向するクロス33の直管部を長く
する)ることにより、不規則流動を緩和させた分岐管部
の概略図である。本実施例の場合にも上記と同様の効果
が達成される。
FIG. 8 shows how to raise the position of the reducer 13 (lengthen the straight pipe part of the cross 33 facing the main pipe 22) so that the irregular flow in the reducer part of the conventional structure is not applied to the header curved pipe 12. FIG. 2 is a schematic diagram of a branch pipe section in which irregular flow is alleviated. In the case of this embodiment as well, effects similar to those described above are achieved.

第9.10図は十字管部及び曲管12よりライサ管24
に分岐する分岐部において、渦の発生、消滅による流れ
の不安定変動を改善するため、第1にクロス上部のレジ
ユーサ部を無くすと共に、クロス部及びライザ管分岐部
に太部を設け、流れのよどみをとつて、不安定変動を改
善するクロス34、分岐部35及びキヤツプ36、分岐
部37を有する例である。
Figure 9.10 shows the riser pipe 24 from the cross pipe section and bent pipe 12.
In order to improve unstable fluctuations in the flow caused by the generation and disappearance of vortices at the branch section where the vortex branches into the This example includes a cross 34, a branch 35, a cap 36, and a branch 37 that eliminate stagnation and improve unstable fluctuations.

第11図は、十字分岐部の不安定な流れを絞り安定化さ
せるために、レジユーサ35を有した構造のPLR系配
管の概略図であり、本実施例でも流れを強制化し、流量
変動を抑制し、上記と同様の効果が達成される。
FIG. 11 is a schematic diagram of a PLR system piping structure having a reducer 35 in order to throttle and stabilize the unstable flow at the cross branch. In this embodiment, the flow is also forced and suppresses flow rate fluctuations. However, the same effect as above is achieved.

(発用の効果) 本発明によれば、十字管部の渦の発生を防止または安定
せしめ、PLR系の流量変動をなくし安定なBWRプラ
ントの運転が可能となる。
(Effects of Activation) According to the present invention, the generation of vortices in the cross pipe section is prevented or stabilized, and flow rate fluctuations in the PLR system are eliminated, making it possible to operate the BWR plant stably.

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

第1図はBWRプラントの従来のPLR系配管の構造図
、第2、3図は第1図に示されるクロスの構造図、第4
、5図はクロス部での冷却材の流れの状態の説明図、第
6、7、8、9、10、11図は本発明の実施例である
。 1…原子炉圧力容器、7…ポンプ、11…クロス、12
…ヘツダ曲管、13…レジユーサ、22…母管、24…
ライザ管、31、32…テイー33、34…クロス、3
5…分岐部、36…キヤツプ。 代理人 弁理士 高橋明夫 第1頁の続き (72)発明者 小玉 郁夫 東京都千代田区神田駿河
台4丁目6番地 株式会社日立製作所内 (72)発明者 根目沢 勲 日立市幸町3丁目1番1
号 株式会社日立製作所日立工場内 (72)発明者 泉山 昭政 日立市幸町3丁目1番1
号 株式会社日立製作所日立工場内 (72)発明者 鈴木 公一 日立市幸町3丁目1番1
号 株式会社日立製作所日立工場内 (72)発明者 小杉 伸夫 日立市幸町3丁目1番1
号 株式会社日立製作所日立工場内 (72)発明者 武原 秀俊 日立市幸町3丁目1番1
号 株式会社日立製作所日立工場内
Figure 1 is a structural diagram of the conventional PLR system piping of a BWR plant, Figures 2 and 3 are structural diagrams of the cross shown in Figure 1, and Figure 4 is a structural diagram of the conventional PLR system piping of a BWR plant.
, 5 is an explanatory diagram of the flow state of the coolant at the cross portion, and FIGS. 6, 7, 8, 9, 10, and 11 are examples of the present invention. 1...Reactor pressure vessel, 7...Pump, 11...Cross, 12
...Header bent pipe, 13...Register, 22...Main pipe, 24...
Riser pipe, 31, 32...Tee 33, 34...Cross, 3
5... Branch, 36... Cap. Agent Patent Attorney Akio Takahashi Continuation of page 1 (72) Inventor Ikuo Kodama 4-6 Kanda Surugadai, Chiyoda-ku, Tokyo Hitachi, Ltd. (72) Inventor Isao Nemezawa 3-1 Saiwaimachi, Hitachi City 1
No. Hitachi Factory, Hitachi, Ltd. (72) Inventor Akimasa Izumiyama 3-1-1 Saiwai-cho, Hitachi City
No.: Hitachi Factory, Hitachi, Ltd. (72) Inventor: Koichi Suzuki 3-1-1 Saiwaimachi, Hitachi City
No. Hitachi Factory, Hitachi, Ltd. (72) Inventor Nobuo Kosugi 3-1-1 Saiwaimachi, Hitachi City
No.: Hitachi Factory, Hitachi, Ltd. (72) Inventor: Hidetoshi Takehara 3-1-1 Saiwaimachi, Hitachi City
No. Hitachi, Ltd. Hitachi Factory

Claims (4)

【特許請求の範囲】[Claims] 1.開口を四方に有する十字分岐部において、第1開口
は再循環ポンプ吐出口に連結している母管に接続され、
その開口と対向する第2開口が、流路断面積が徐々に減
少するレジユーサ部とから成り前記レジユーサ部の流路
断面積が最小となる部分に、前記レジユーサと一体にラ
イザー管を形成しまた、前記母管とレジユーサが接続さ
れていない前記十字分岐部の二つの第3、4開口には、
それぞれヘツダー曲管が接続されている。沸騰水型原子
力プラント(以下、BWRプラントと呼ぶ)の再循環配
管系(以下、PLR配管系と呼ぶ)において、十字分岐
部の流量配分を常に安定させる構造を有することを特徴
とする、BWRプラントのPLR配管系。
1. In the cross branch having openings on all sides, the first opening is connected to a main pipe connected to a recirculation pump outlet;
A second opening facing the opening is formed of a reducer portion whose flow passage cross-sectional area gradually decreases, and a riser pipe is formed integrally with the resistor at a portion where the flow passage cross-sectional area of the reducer portion is the minimum. , the two third and fourth openings of the cross branch to which the main pipe and the reducer are not connected,
A header bent pipe is connected to each. A BWR plant characterized by having a structure that always stabilizes flow rate distribution in a cross branch in a recirculation piping system (hereinafter referred to as a PLR piping system) of a boiling water nuclear power plant (hereinafter referred to as a BWR plant). PLR piping system.
2.前記十字分岐部において、十字分岐をなくし流量配
分を常に安定させる構造を有することを特徴とする特許
請求の範囲第1項記載のBWRプラントのPLR配管系
2. 2. The PLR piping system for a BWR plant according to claim 1, wherein the cross branch part has a structure that eliminates the cross branch and always stabilizes flow rate distribution.
3.前記十字分岐部において、枝部にふくらみをつけ、
分岐部の流量配分を安定させる構造を有することを特徴
とする特許請求の範囲第1項記載のBWRプラントのP
LR配管系。
3. At the cross-branched part, a bulge is added to the branch part,
P of the BWR plant according to claim 1, characterized in that it has a structure that stabilizes the flow distribution of the branch part.
LR piping system.
4.前記十字分岐部において、第2開口に設けられたレ
ジユーサ部を十字分岐部から離れた位置に設け分岐部の
流量配分を安定させる構造を有することを特徴とする特
許請求の範囲第1項記載のBWRプラントのPLR配管
系。
4. Claim 1, characterized in that the cross branch part has a structure in which a reducer part provided at the second opening is provided at a position away from the cross branch part to stabilize flow distribution in the branch part. PLR piping system of BWR plant.
JP58196601A 1983-10-19 1983-10-19 Recirculating piping system of boiling-water type nuclear power plant Pending JPS6088389A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58196601A JPS6088389A (en) 1983-10-19 1983-10-19 Recirculating piping system of boiling-water type nuclear power plant

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58196601A JPS6088389A (en) 1983-10-19 1983-10-19 Recirculating piping system of boiling-water type nuclear power plant

Publications (1)

Publication Number Publication Date
JPS6088389A true JPS6088389A (en) 1985-05-18

Family

ID=16360455

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58196601A Pending JPS6088389A (en) 1983-10-19 1983-10-19 Recirculating piping system of boiling-water type nuclear power plant

Country Status (1)

Country Link
JP (1) JPS6088389A (en)

Similar Documents

Publication Publication Date Title
JPH05157871A (en) Fuel spacer
JPS6088389A (en) Recirculating piping system of boiling-water type nuclear power plant
EP0146134B1 (en) Piping branch structure
JPS6195284A (en) Recirculating piping for boiling water type nuclear power plant
JPH08135883A (en) Piping joint
JP3195073B2 (en) Fuel spacer
JPS60190893A (en) Recirculating piping for boiling-water type nuclear power plant
JPS61160695A (en) Crossed piping structure
JPH08210577A (en) Plant piping system
JPS6088206A (en) Flow fluctuation supplessing method and construction of branch pipes in recycling piping system in bwr plant
JPS60147696A (en) Recirculating piping system for coolant of nuclear power plant
JPS60146195A (en) Recirculating piping system for coolant of nuclear power plant
JPS6138594A (en) Boiling-water type nuclear power plant
JPS59136676A (en) Natural circulation type water cooled reactor
SU1740956A1 (en) Method of thermal-hydraulic stabilization of steam- generating channel
JPS60190894A (en) Recirculating piping for boiling-water type nuclear power plant
JPH06308276A (en) Nozzle of reactor pressure vessel
JPS60198491A (en) Reactor recirculating system piping
JPS61175593A (en) Crossed branch tube of recirculation system of boiling watertype nuclear power plant
JPS60146194A (en) Recirculating piping system of boiling water type nuclear power plant
JPS6148697A (en) Crossed piping structure
JPH0531752B2 (en)
JPH0393B2 (en)
JPS60164297A (en) Crossed piping structure
JPS60161593A (en) Piping structure of recirculation system, etc. for nuclear reactor