JPH046496A - Spontaneous circulation type boiling water reactor - Google Patents

Spontaneous circulation type boiling water reactor

Info

Publication number
JPH046496A
JPH046496A JP2107406A JP10740690A JPH046496A JP H046496 A JPH046496 A JP H046496A JP 2107406 A JP2107406 A JP 2107406A JP 10740690 A JP10740690 A JP 10740690A JP H046496 A JPH046496 A JP H046496A
Authority
JP
Japan
Prior art keywords
steam
water
reactor
cylindrical bodies
dome
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
JP2107406A
Other languages
Japanese (ja)
Inventor
Masaru Kato
賢 加藤
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
Toshiba Corp
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 Toshiba Corp filed Critical Toshiba Corp
Priority to JP2107406A priority Critical patent/JPH046496A/en
Publication of JPH046496A publication Critical patent/JPH046496A/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

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

PURPOSE:To reduce a pressure loss and thereby to lessen reduction of a spontaneous circulation flow rate and to improve safety of operation by a method wherein a steam-water mixed liquid produced from a core is made to meander several times by porous cylindrical bodies and led to a steam dome in the upper part of a reactor pressure vessel. CONSTITUTION:A curved blind plate 22 and porous cylindrical bodies 23 are provided between the upper part of a shroud 17 and a steam dome 18, and the porous cylindrical bodies 23a to 23e being different in the inside diameter are disposed in a plurality of layers in the axial direction concentrically, while each of the cylindrical bodies 23a to 23e is provided with a number of channel holes 24a to 24e. In a normal operation, cooling water boiling in a core 14 rises through a rise part 15. Water vapor containing a liquid droplet running out of a liquid surface flows laterally since the dome-shaped blind plate 22 is provided above, and it is separated into steam and water until it flows to the steam dome 18 through the cylindrical bodies 23 provided in a plurality of layers.

Description

【発明の詳細な説明】 〔発明の目的〕 (産業上の利用分野) 本発明は炉心から発生する気水温合流をそれぞれ蒸気と
水に分離するための気水分離器を改良した自然循環形沸
騰水型原子炉に関する。
[Detailed Description of the Invention] [Objective of the Invention] (Industrial Application Field) The present invention is a natural circulation type boiling system which is an improved steam and water separator for separating the combined temperature of air and water generated from a reactor core into steam and water, respectively. Regarding water reactors.

(従来の技術) 沸騰水型原子炉に用いられている従来の気水分離器4は
第4図に示すようにシュラウド25のヘット部26に複
数配設されている。すなわち、炉心1から発生する蒸気
と水の混合流は上部プレナム2に入り、シュラウドヘッ
ト部26に林立するスタンドパイプ3を通って気水分離
器4に流入する。
(Prior Art) A plurality of conventional steam/water separators 4 used in a boiling water nuclear reactor are arranged in a head portion 26 of a shroud 25, as shown in FIG. That is, a mixed flow of steam and water generated from the reactor core 1 enters the upper plenum 2, passes through the stand pipes 3 standing in the shroud head portion 26, and flows into the steam separator 4.

気水分離器4は第5図に示すような構造を有しており、
スタンドパイプ3から流入する蒸気と水の混合流は、ス
タンドパイプ3と同軸同径で接続するライザ5から旋回
羽根6に至り、この旋回羽根6により旋回力を与えられ
、螺旋状に旋回しながら旋回胴7の内部を上昇していく
。この際、比重の大きい水は遠心力によって旋回胴7の
内壁に押し付けられ、比重の小さい蒸気は旋回胴7の中
心部(コア)を流れるために気水分離が行われる。
The steam/water separator 4 has a structure as shown in FIG.
The mixed flow of steam and water flowing from the standpipe 3 reaches the swirling vane 6 from the riser 5, which is connected coaxially and with the same diameter as the standpipe 3, and is given a swirling force by the swirling vane 6, and as it swirls in a spiral shape. It ascends inside the rotating trunk 7. At this time, water with a high specific gravity is pressed against the inner wall of the rotating body 7 by centrifugal force, and steam with a low specific gravity flows through the center (core) of the rotating body 7, so that steam and water separation is performed.

旋回胴7の上方には分離した水を徘呂するための排水口
8が設置゛」られている。旋回胴7の内壁を伝って流れ
てくる水は排水口8し、4流入し、旋回胴゛7と外筒9
との間に形成されている環状流路10の上方に流れMト
水さ第1、る。一方、旋回胴′7の中心部を流れる蒸気
は旋回胴7の上方の蒸気排出r’−1111ニー入り、
蒸気−1出管12を経て蒸気ドーム(図示ヤ7ず)に流
入する。
A drain port 8 is installed above the rotating body 7 to drain the separated water. The water flowing along the inner wall of the rotating body 7 flows through the drain port 8 and flows into the rotating body 7 and the outer cylinder 9.
The water flows above the annular flow path 10 formed between the first and second channels. On the other hand, the steam flowing through the center of the rotating body 7 enters the steam exhaust r'-1111 knee above the rotating body 7.
Steam 1 flows into a steam dome (not shown) via an outlet pipe 12.

(発明が解決【7、ようとする課題) 以1−説明した過程おいて蒸気と水の混合流は大きな流
動抵抗を受ける。特にj一部ブレナAs 2からスタン
ドパイプ:3に流入する際の流電配分し起因する圧力損
失および縮流に起因する圧力損失、スタンドバイブ3を
通過する際の圧力損失および旋回羽根を通過する際の圧
力損失が太きい。ハニカ損失が大きいと自然#M環流量
が減少するため沸騰水型原子炉の熱水力学的安定性が悪
くなる課題がある。
(Problems to be Solved by the Invention [7]) In the process described in 1-1 below, the mixed flow of steam and water is subjected to large flow resistance. In particular, the pressure loss caused by current distribution when flowing from Brenna As 2 to 3, the pressure loss caused by contraction, the pressure loss when passing through stand vibe 3, and the swirling vane. The pressure loss during operation is large. If the honeycomb loss is large, the natural #M recirculation flow rate decreases, which poses a problem in that the thermal-hydraulic stability of the boiling water reactor deteriorates.

本発明は」−記課題な解決するためになされたもので、
その目的は気水分離器と蒸気乾燥器を兼ね。
The present invention has been made to solve the problems mentioned above.
Its purpose is to serve as both a steam separator and a steam dryer.

圧力損失の低減を図って自然循環流電の低減を極力小さ
くするとともに、運転の安定性を向卜せしめるようにし
た自然循環形佛騰水型原−L炉4提供することにある。
It is an object of the present invention to provide a natural circulation type buttonic water type raw-L reactor 4 which is designed to reduce pressure loss, minimize the reduction in natural circulation current, and improve operational stability.

〔発明の構成〕[Structure of the invention]

(課題を解決1−るための手段) 本発明は原子・炉ルカ容器内1、こ配置された炉心と、
この炉心の回1]を囲むシュラウドと、このシュラウ1
−の内側でii(記炉心の上部に位置した冷却水および
水蒸気のl−7M部と、前記シコラウ1−および原子炉
圧力容器の間に形成された円環状のダウンカマど、この
ダウンカンの上方につながる下部ブレナムとからなる自
然循環型原子炉に用いる低水分離器において、前記原子
炉圧力容器の、]一部鏡板の下部と前記ト、封部との間
にドーム状盲板を設置は、この盲板の周辺部のT側とT
hi記原了炉圧力容器の内壁との間し、゛多孔円筒体を
複数層重ね、前記多孔円筒体の子れぞれの孔は千鳥状に
配列し7でなることを特徴と憤る。
(Means for Solving the Problem 1) The present invention provides a nuclear reactor vessel (1), a reactor core arranged therein,
The shroud surrounding this reactor core [1] and this shroud 1
- inside the ii In a low water separator used in a natural circulation nuclear reactor consisting of a connected lower blennium, a dome-shaped blind plate is installed between the lower part of the head plate of the reactor pressure vessel and the sealing part of the reactor pressure vessel. The T side of the peripheral part of this blind plate and the T side
hi The feature is that a plurality of porous cylindrical bodies are stacked on top of each other, and the holes of each of the porous cylindrical bodies are arranged in a staggered pattern.

また、円筒体も・複数層に重ねたそれぞれの円筒体の孔
径は手鋸が大きく、ト側1向うにしたがって徐々に小さ
くなるよ−)に設けられていることを特徴とする5 (作 用) 本発明は、Jt7″−炉圧力容器の炉心上部を上述した
構造にするごとにより、炉心から発生した気水混合流が
数回多孔円筒体を蛇行しなから加」′炉圧力容器上部の
蒸気ドームに導かおる。これによって、蒸気と水が効率
的に分1aさJll、蒸気が蒸気ドー11へ、液滴がダ
ウンカマに流入配る。
In addition, the cylindrical body is also characterized in that the hole diameter of each cylindrical body stacked in multiple layers is large in the hand saw and gradually becomes smaller as it goes toward the front side. ) The present invention has the above-mentioned structure for the upper part of the reactor pressure vessel of the Jt7" reactor pressure vessel, so that the mixed flow of steam and water generated from the reactor core does not meander around the porous cylinder several times, and then the upper part of the reactor pressure vessel It will lead you to the steam dome. As a result, steam and water are efficiently distributed, the steam flows into the steam dome 11, and the droplets flow into the downcomer.

この気液分離過程で、通常運転時に炉心か皐゛、発生す
る気水混合流を圧力損失の低減を計っCぞhぞれ蒸気と
水に分離する二とができる。
In this gas-liquid separation process, the mixed flow of steam and water that is generated in the reactor core during normal operation can be separated into steam and water, respectively, in order to reduce pressure loss.

(実施例) 第1図および第2図を参照しながら本発明に係る自然循
環形沸騰水型原f炉の〜実施@を説明する。
(Example) With reference to FIGS. 1 and 2, implementation of a natural circulation boiling water type f-reactor according to the present invention will be described.

第1図において、原子炉圧力容器13内には炉心14が
配置されでおり、この炉心14で加熱された冷却材およ
び水蒸気の−1−封部15に沿って原子炉ハー力容器1
3との間に形成され、上昇部15と冷却材が1;降する
ダウンカマとを隔離するための長尺円筒状シュラウドl
’7が炉心14を基点として設けら紅ている。ジュラウ
[・1゛7のドブJど原子炉圧力容器13の1−端を閉
塞する上1部鏡板13aとの間には蒸気1−−ム18が
1没けられ、この蒸気ト・−ム18内の蒸父、は主蒸気
管19から図示しごないタービンへ送られ、る。タビン
で仕事を終えた蒸気間復水器で復水され給水管20から
冷却材どして原子−炉圧力容器13内に流入する9この
冷却材は原子炉圧力容器1:3内からダウンカマ16を
流下し、ド部ブ1ノサム21を通って炉心14内に流入
する。
In FIG. 1, a reactor core 14 is disposed within a reactor pressure vessel 13, and the reactor pressure vessel
an elongated cylindrical shroud l formed between the rising part 15 and the downcomer from which the coolant falls;
'7 is set with the core 14 as the base point. A steam tom 18 is inserted between the upper head plate 13a that closes the first end of the reactor pressure vessel 13, and the drain J at J. The steamer in 18 is sent from a main steam pipe 19 to a turbine (not shown). After finishing its work in the turbine, water is condensed in the steam condenser, and the coolant flows from the water supply pipe 20 into the reactor pressure vessel 13.9 This coolant flows from inside the reactor pressure vessel 1:3 into the downcomer 16. flows down and flows into the reactor core 14 through the groove 1 nosum 21.

シュラウド17 (7) 、、、、、ll:。方と蒸気
ドーム18との間にはわん曲状の盲板22と多孔円筒体
23が設けられており、多孔円筒体23は第2図に部分
的番、:拡大しで示【、たよ−うな構造番;”7なって
いる。
Shroud 17 (7) , , , , ll:. A curved blind plate 22 and a porous cylindrical body 23 are provided between the steam dome 18 and the steam dome 18. The porous cylindrical body 23 is partially enlarged in FIG. Una structure number: 7.

すなわち、内径が異な−)でいる多孔円筒体2:bi。That is, the porous cylindrical bodies 2:bi have different inner diameters.

23b、 23e、 23d、 2釦が同心円的に軸方
向に複層とな−〕°C配列されており、各々の円筒体2
3a=・23eにば多数の流路孔24a□24eが設し
づられたものから構成される装置 なお、第1図および第2図中実線矢印−は冷却材の流れ
を、破線矢印→は蒸気の流れをそれぞれ示している。つ
ぎに上記実施例における自然循環形沸騰水型原子炉の作
用を説明する。
23b, 23e, 23d, 2 buttons are arranged concentrically in multiple layers in the axial direction, and each cylindrical body 2
3a=・23e is a device in which a large number of flow passage holes 24a□24e are provided. In FIGS. 1 and 2, the solid line arrow - indicates the flow of coolant, and the dashed line arrow → indicates the flow of steam. Each flow is shown below. Next, the operation of the natural circulation boiling water reactor in the above embodiment will be explained.

通常運転時においては、炉心14で沸騰した冷却水は上
昇部15を上昇し、液面Qを流出した液滴を含んだ水蒸
気は上方にドーム状の盲板22が設置されているため横
方向に流れ、複数層に配設された多孔円筒体23を通っ
て蒸気ドーム18に流れるまでにそれぞれ蒸気と水に分
離される。詳しくは第2図に示すように、気水温合液は
まず多孔同筒体23aの流路孔24aを通る。流路孔2
4aを通過した気水混合液は次の多孔円筒体23bの壁
に衝突し、蒸気は上方へ、液滴は下方に落下分離される
。分離した蒸気および液滴は他の流路孔24aから流入
してくる気水混合液と衝突し、次の流路孔24bに入る
During normal operation, cooling water boiled in the core 14 ascends the rising section 15, and water vapor containing droplets that has flowed out of the liquid surface Q is disposed of in a lateral direction due to the dome-shaped blind plate 22 installed above. The water is separated into steam and water before flowing into the steam dome 18 through the porous cylindrical body 23 arranged in multiple layers. Specifically, as shown in FIG. 2, the mixed liquid at temperature of air and water first passes through the channel hole 24a of the porous cylinder 23a. Channel hole 2
The steam/water mixture that has passed through 4a collides with the wall of the next porous cylindrical body 23b, and the steam falls upward and the droplets fall downward and are separated. The separated vapor and droplets collide with the steam/water mixture flowing in from another channel hole 24a, and enter the next channel hole 24b.

さらに多孔円筒体23cの壁に衝突して同様に蒸気・水
が分離される。これらの作用を繰り返す行われることに
より効率的に蒸気・水が分離される。なお、自然循環運
転特性では従来の沸騰水型原子炉に比べ気水混合液の上
昇速度が遅いために、この程度の簡単な構造でも気水分
離および蒸気乾燥の機能ができる。
Furthermore, it collides with the wall of the porous cylindrical body 23c, and steam and water are similarly separated. By repeating these actions, steam and water can be efficiently separated. In addition, due to the natural circulation operation characteristics, the rate of rise of the steam-water mixture is slower than in conventional boiling water reactors, so even such a simple structure can perform the functions of steam-water separation and steam drying.

本実施例においては各々の多孔円筒体の孔径は同一寸法
としたが、他の実施例としては第3図(第2図のB矢視
図)に示すように、圧力損失の低減と蒸気・水の分離効
果を良好にする目的で、複数層の各多孔円筒体23の流
路孔24の孔径を下側に大きく、上側に向うにしたがっ
て徐々に小さくしてもよい。
In this example, the pore diameters of each porous cylinder were made to be the same size, but as shown in FIG. In order to improve the water separation effect, the diameter of the channel hole 24 of each porous cylindrical body 23 of the plurality of layers may be made larger toward the bottom and gradually smaller toward the top.

〔発明の効果〕〔Effect of the invention〕

本発明によれば、通常運転時においては5気水分離器の
性能を損なうことなく、従来の気液分離器および蒸気乾
燥器を削除することにより、圧力損失を低減させること
ができるので、沸騰水型原子炉の自然循環運転特性の向
上が図れ、信頼性も向上させることができる。また、炉
内構造物が簡素化してコストダウンを図ることができる
According to the present invention, during normal operation, pressure loss can be reduced by eliminating the conventional gas-liquid separator and steam dryer without impairing the performance of the 5-gas water separator. The natural circulation operation characteristics of water reactors can be improved, and reliability can also be improved. Further, the reactor internal structure can be simplified and costs can be reduced.

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

第1図は本発明に係る自然循環形沸騰水型原子炉の一実
施例を示す概念図、第2図は第1図のA部を拡大して示
す縦断面図、第3図は第2図の8方向から見た側面図、
第4図は従来の沸騰水型原子炉の炉心部から気水分離器
までを示す側面図、第5図は第4図における気水分離器
を示す縦断面である。 13・・・原子炉圧力容器  14・・炉心15・・・
上昇部      16・・ダウンカマ17・・・シュ
ラウド    18・・・蒸気ドーム19・・・主蒸気
管     20・・給水管21・・下部プレナム  
 22・・・盲板23.23a〜23e・・・多孔円筒
体24 、24a−24e・・・流路孔 代理人 弁理士 則 近 憲 佑 第 、3 閃
FIG. 1 is a conceptual diagram showing an embodiment of a natural circulation boiling water nuclear reactor according to the present invention, FIG. 2 is an enlarged vertical cross-sectional view of section A in FIG. Side view seen from 8 directions in the figure,
FIG. 4 is a side view showing a conventional boiling water reactor from the core to a steam separator, and FIG. 5 is a longitudinal cross-section showing the steam water separator in FIG. 13...Reactor pressure vessel 14...Reactor core 15...
Rising part 16...Downcomer 17...Shroud 18...Steam dome 19...Main steam pipe 20...Water supply pipe 21...Lower plenum
22... Blind plate 23. 23a-23e... Porous cylindrical body 24, 24a-24e... Channel hole agent Patent attorney Noriyuki Ken Yudai, 3 Flash

Claims (1)

【特許請求の範囲】[Claims] 原子炉圧力容器内に配置された炉心と、この炉心の回り
を囲むシュラウドと、このシュラウドの内側で前記炉心
の上部に位置した冷却水および水蒸気の上昇部と、前記
シュラウドおよび原子炉圧力容器の間に形成された円環
状のダウンカマと、このダウンカマの下方につながる下
部プレナムとからなる自然循環形沸騰水型原子炉におい
て、前記原子炉圧力容器の上部鏡板の下部と前記上昇部
との間にドーム状盲板を設け、この盲板の周辺部の下側
と前記原子炉圧力容器の内壁との間に多孔円筒体を複数
層重ね、前記多孔円筒体のそれぞれの孔は千鳥状に配列
されてなることを特徴とする自然循環形沸騰水型原子炉
A reactor core disposed within a reactor pressure vessel, a shroud surrounding the reactor core, a rising portion for cooling water and steam located above the reactor core inside the shroud, and a reactor core disposed within the reactor pressure vessel; In a natural circulation boiling water reactor comprising an annular downcomer formed between and a lower plenum connected below the downcomer, there is a gap between the lower part of the upper head plate of the reactor pressure vessel and the rising part. A dome-shaped blind plate is provided, and a plurality of layers of porous cylinders are stacked between the lower side of the peripheral part of the blind plate and the inner wall of the reactor pressure vessel, and the holes of each of the porous cylinders are arranged in a staggered manner. A natural circulation boiling water reactor that is characterized by
JP2107406A 1990-04-25 1990-04-25 Spontaneous circulation type boiling water reactor Pending JPH046496A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP2107406A JPH046496A (en) 1990-04-25 1990-04-25 Spontaneous circulation type boiling water reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP2107406A JPH046496A (en) 1990-04-25 1990-04-25 Spontaneous circulation type boiling water reactor

Publications (1)

Publication Number Publication Date
JPH046496A true JPH046496A (en) 1992-01-10

Family

ID=14458340

Family Applications (1)

Application Number Title Priority Date Filing Date
JP2107406A Pending JPH046496A (en) 1990-04-25 1990-04-25 Spontaneous circulation type boiling water reactor

Country Status (1)

Country Link
JP (1) JPH046496A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP1341187A2 (en) 2002-02-14 2003-09-03 General Electric Company Apparatus and methods for controlling flow in BWR steam dryers

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP1341187A2 (en) 2002-02-14 2003-09-03 General Electric Company Apparatus and methods for controlling flow in BWR steam dryers
EP1341187A3 (en) * 2002-02-14 2003-11-05 General Electric Company Apparatus and methods for controlling flow in BWR steam dryers
US6810837B2 (en) 2002-02-14 2004-11-02 General Electric Company Apparatus and methods for controlling flow in BWR steam dryers

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