JPS63143403A - Steam generator - Google Patents

Steam generator

Info

Publication number
JPS63143403A
JPS63143403A JP28775186A JP28775186A JPS63143403A JP S63143403 A JPS63143403 A JP S63143403A JP 28775186 A JP28775186 A JP 28775186A JP 28775186 A JP28775186 A JP 28775186A JP S63143403 A JPS63143403 A JP S63143403A
Authority
JP
Japan
Prior art keywords
steam generator
water
secondary water
sludge
tube 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
JP28775186A
Other languages
Japanese (ja)
Inventor
田口 耕世
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 JP28775186A priority Critical patent/JPS63143403A/en
Publication of JPS63143403A publication Critical patent/JPS63143403A/en
Pending legal-status Critical Current

Links

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】 [発明の目的] (産業上の利用分野) 本発明は加圧水型原子炉で使用される蒸気発生器におい
て、管板の形状を改善してスラッジの堆積を抑制した蒸
気発生器に関する。
[Detailed Description of the Invention] [Objective of the Invention] (Industrial Application Field) The present invention provides a steam generator for use in a pressurized water nuclear reactor, in which the shape of the tube plate is improved to suppress the accumulation of sludge. Regarding the generator.

(従来の技術) 加圧水型原子炉では蒸気タービンを駆動するために原子
炉で発生させた高温高圧水を蒸気に変換する蒸気発生器
が使用される。
(Prior Art) A pressurized water nuclear reactor uses a steam generator that converts high-temperature, high-pressure water generated in the reactor into steam to drive a steam turbine.

第2図は従来の蒸気発生器の仝体溝成を示すもので、容
器1の内筒2内には多数本のU字型伝熱管3が配置され
、所々をサポート4で支持されている。伝熱管3の両端
はそれぞれ管板5を介して容器1下端の1次水入口6ま
たは1次水出ロアに連通している。
FIG. 2 shows the structure of a conventional steam generator. A large number of U-shaped heat transfer tubes 3 are arranged inside an inner cylinder 2 of a container 1, supported in places by supports 4. . Both ends of the heat transfer tubes 3 communicate with a primary water inlet 6 or a primary water outlet lower end at the lower end of the container 1 via tube sheets 5, respectively.

容器1の上半部内にはセパレータ8およびドライヤ9が
設置されている。図中、符号10は2次水入口、11は
蒸気用l]を示す。
A separator 8 and a dryer 9 are installed in the upper half of the container 1. In the figure, reference numeral 10 indicates a secondary water inlet, and 11 indicates a steam l.

原子炉(図示せず)で発生した高温高圧水は、1次水入
口6から容器1内に入り、管板5を介してU字型の伝熱
管3内を流れ、2次水との熱交換によって冷却された俊
、1次水出「17から流れ出る。
High-temperature, high-pressure water generated in a nuclear reactor (not shown) enters the container 1 from the primary water inlet 6, flows through the U-shaped heat transfer tube 3 via the tube plate 5, and exchanges heat with the secondary water. Shun, who has been cooled by the exchange, flows out of the primary water supply "17.

一方、低温の2次水は2次水入口10から容器1内に流
入し、容器1の中心部、および容器1と内筒2の間のダ
ウンカマ12を下降し、管板5上で反転し、内筒2内を
上昇スる。この2次水は伝熱管3内の高温の1次水から
熱を受は取って高温になるが、圧ツノはほぼ一定である
から飽和圧力以下となり沸騰する。この気液2相流は上
昇を続け、セパレータ8により蒸気と液体(水)に分離
され、液体は再び容器内を下降する。一方、蒸気はざら
にドライA79により乾き度を高められた後、蒸気出口
11からタービン(図示Uず)へ送られる。
On the other hand, low-temperature secondary water flows into the container 1 from the secondary water inlet 10, descends through the center of the container 1 and the downcomer 12 between the container 1 and the inner cylinder 2, and is turned over on the tube plate 5. , ascends inside the inner cylinder 2. This secondary water receives heat from the high-temperature primary water in the heat transfer tube 3 and becomes high in temperature, but since the pressure angle is approximately constant, the pressure falls below the saturation pressure and boils. This gas-liquid two-phase flow continues to rise and is separated into vapor and liquid (water) by the separator 8, and the liquid descends inside the container again. On the other hand, the dryness of the steam is increased by the rough dryer A79, and then the steam is sent from the steam outlet 11 to the turbine (not shown).

(発明が解決しようとする問題点) 上述のように伝熱管3の中心部およびダウンカマ12を
下降してきた2次水20は第3図に示すように管板5の
上方にて反転し、上昇流21となる。
(Problems to be Solved by the Invention) The secondary water 20 that has descended through the center of the heat transfer tube 3 and the downcomer 12 as described above is reversed above the tube plate 5 and rises as shown in FIG. It becomes flow 21.

この上昇流21は第4図の2次水流線30に示すように
分布するので、管板5の中央部から所定の半径上に2次
水澱み部31が生じ、その部分に、第3図および第5図
に示すようなスラッジ40の堆積物か生じる。このスラ
ッジ40は第6図に示すように伝熱管3の回りの管板5
上に堆積し、その上部は固液混合層41としてのスラッ
ジ40で覆われることになる。この固液混合層41は流
れによって多少上下することになり、ぞの部分で2次水
中の塩素イオンが濃縮され、伝熱管3に局所的な腐蝕箇
所3aを生じざぜるという問題があっlこ。
Since this upward flow 21 is distributed as shown in the secondary water flow line 30 in FIG. A deposit of sludge 40 as shown in FIG. 5 is formed. As shown in FIG.
The sludge 40 is deposited on top, and the top thereof is covered with a sludge 40 as a solid-liquid mixed layer 41. This solid-liquid mixed layer 41 moves up and down somewhat due to the flow, and there is a problem in that chlorine ions in the secondary water are concentrated in these parts, causing localized corrosion spots 3a in the heat exchanger tubes 3. .

[発明の構成] (問題点を解決するための手段) 本発明に係わる蒸気発生器は、加圧水型原子炉で使用さ
れる蒸気発生器において、1次水と2次水を分離すると
共に、多数のU字型伝熱管を固定する管板の上面形状を
この管板上の2次水流量分布に合せてなだらかな凸状に
したことを特徴とするものである。
[Structure of the Invention] (Means for Solving the Problems) A steam generator according to the present invention separates primary water and secondary water in a steam generator used in a pressurized water nuclear reactor, and also separates primary water and secondary water. The upper surface of the tube plate to which the U-shaped heat exchanger tube is fixed is shaped into a gentle convex shape in accordance with the secondary water flow rate distribution on the tube plate.

(作 用) 本発明によれば蒸気発生器の管板には、2次水の澱み部
分にスラッジが堆積しずらくなり、管板上のスラッジに
起因する伝熱管の腐蝕を防止することができる。
(Function) According to the present invention, it is difficult for sludge to accumulate in the stagnant portion of secondary water on the tube sheet of a steam generator, and corrosion of the heat exchanger tubes caused by sludge on the tube sheet can be prevented. can.

(実施例) 本発明に係わる蒸気発生器の実施例を第1図に示す。こ
の図は従来例を示す第3図に対応するもので、管板5の
上面は、従来、澱み部31が生じやすかった半径R部分
がリング状に高くなるよう凸部5aを形成されている。
(Example) An example of a steam generator according to the present invention is shown in FIG. This figure corresponds to FIG. 3 showing a conventional example, and the upper surface of the tube plate 5 is formed with a convex portion 5a so that the radius R portion where the stagnation portion 31 is likely to occur is raised in a ring shape. .

なお、それ以外の構成は第2図におけると同様である。Note that the other configurations are the same as in FIG. 2.

上述のように構成した蒸気発生器において、ダウンカマ
12および伝熱管3の中央部からの下降流20は管板5
の上面近傍で反転し、上昇流21となる。従来例では2
次水の流れ分布に起因する澱み部31ができたが、本発
明ではそこになだらかな凸部5a@設けであるので、こ
の部分にスラッジが堆積することを防ぐことができる。
In the steam generator configured as described above, the downflow 20 from the center of the downcomer 12 and the heat exchanger tubes 3 flows through the tube plate 5.
The flow reverses near the upper surface of the flow and becomes an upward flow 21. In the conventional example, 2
Although a stagnation part 31 is formed due to the flow distribution of the water, the present invention provides a gentle convex part 5a@ there, so that it is possible to prevent sludge from accumulating in this part.

[発明の効果] 上述の如く、本発明によれば、管板上にスラッジの堆積
をなくすことが可能でおり、ぞの結果、上述のようなス
ラッジの堆積に起因する伝熱管の局所的な腐蝕等を防止
することができる。従って伝熱管の健全性を長期間維持
することができ、蒸気発生器の長寿命化、信頼性の向上
がはかれる上、供用期間中検査の作業の簡略化、短縮が
可能となる。
[Effects of the Invention] As described above, according to the present invention, it is possible to eliminate the accumulation of sludge on the tube sheet, and as a result, the localization of the heat exchanger tubes caused by the accumulation of sludge as described above can be eliminated. Corrosion etc. can be prevented. Therefore, the soundness of the heat exchanger tubes can be maintained for a long period of time, the life of the steam generator can be extended, and the reliability can be improved, and inspection work during the service life can be simplified and shortened.

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

第1図は本発明の蒸気発生器の要部の実施例を示す縦断
面図、第2図は蒸気発生器の全体構成を示す一部切欠斜
視図、第3図は従来の蒸気発生器における管板の形状と
そこに堆積するスラッジの分布を例示する縦断面図、第
4図は従来の蒸気発生器にLBける2次水流線を示す説
明図、第5図は第3図のv−v線に沿う横断面図、第6
図は従来の蒸気発生器におレノる管板上に堆積したスラ
ッジと伝熱管との関係を示す縦断面図である。 1・・・・・・・・・容器 2・・・・・・・・・内筒 3・・・・・・・・・伝熱管 4・・・・・・・・・サボー1〜 5・・・・・・・・・管板 5a・・・・・・凸部 6・・・・・・・・・1次水入ロ ア・・・・・・・・・1次水出口 8・・・・・・・・・セパレータ 9・・・・・・・・・ドライヤ 10・・・・・・・・・2次水入口 11・・・・・・・・・蒸気出口 12・・・・・・・・・ダウンカマ 20・・・・・・・・・2次水下陪流 21・・・・・・・・・2次水上昇流 31・・・・・・・・・澱み部 40・・・・・・・・・スラッジ 代理人 弁理士 則 近 憲 佑 同  三俣弘文 第1図 第2図 第4図
Fig. 1 is a longitudinal sectional view showing an embodiment of the main parts of the steam generator of the present invention, Fig. 2 is a partially cutaway perspective view showing the overall structure of the steam generator, and Fig. 3 is a conventional steam generator. A vertical cross-sectional view illustrating the shape of the tube sheet and the distribution of sludge deposited thereon, FIG. 4 is an explanatory diagram showing secondary water flow lines at LB in a conventional steam generator, and FIG. Cross-sectional view along the v line, No. 6
The figure is a longitudinal sectional view showing the relationship between heat exchanger tubes and sludge deposited on a tube sheet in a conventional steam generator. 1...... Container 2... Inner tube 3... Heat transfer tube 4... Sabo 1-5. ......Tube plate 5a...Convex portion 6...Primary water inlet lower......Primary water outlet 8... ......Separator 9...Dryer 10...Secondary water inlet 11...Steam outlet 12...・・・・・・Downcomer 20・・・・・・Secondary water downward flow 21・・・・・・Secondary water upward flow 31・・・・・・Stagnation part 40・・・・・・・・・Sludge agent Patent attorney Nori Chika Ken Yudo Hirofumi Mitsumata Figure 1 Figure 2 Figure 4

Claims (2)

【特許請求の範囲】[Claims] (1)加圧水型原子炉で使用される蒸気発生器において
、1次水と2次水を分離すると共に、多数のU字型伝熱
管を固定する管板の上面形状をこの管板上の2次水流量
分布に合せてなだらかな凸状にしたことを特徴とする蒸
気発生器。
(1) In a steam generator used in a pressurized water reactor, the upper surface shape of the tube plate that separates primary water and secondary water and fixes a large number of U-shaped heat transfer tubes is A steam generator characterized by a gentle convex shape that matches the water flow distribution.
(2)管板の中心から半径R上の上面が凸状にされてい
ることを特徴とする特許請求の範囲第1項記載の蒸気発
生器。
(2) The steam generator according to claim 1, wherein the upper surface at a radius R from the center of the tube plate is convex.
JP28775186A 1986-12-04 1986-12-04 Steam generator Pending JPS63143403A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP28775186A JPS63143403A (en) 1986-12-04 1986-12-04 Steam generator

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP28775186A JPS63143403A (en) 1986-12-04 1986-12-04 Steam generator

Publications (1)

Publication Number Publication Date
JPS63143403A true JPS63143403A (en) 1988-06-15

Family

ID=17721288

Family Applications (1)

Application Number Title Priority Date Filing Date
JP28775186A Pending JPS63143403A (en) 1986-12-04 1986-12-04 Steam generator

Country Status (1)

Country Link
JP (1) JPS63143403A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2015515604A (en) * 2012-02-15 2015-05-28 コリア ハイドロ アンド ニュークリア パワー カンパニー リミティッド Sludge reduction steam generator and method for manufacturing tube sheet for sludge reduction steam generator

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2015515604A (en) * 2012-02-15 2015-05-28 コリア ハイドロ アンド ニュークリア パワー カンパニー リミティッド Sludge reduction steam generator and method for manufacturing tube sheet for sludge reduction steam generator

Similar Documents

Publication Publication Date Title
JPS6038505A (en) Steam generator
US4308914A (en) Double plate flow distributor
JPS5823559B2 (en) Heat exchanger
JPS63143403A (en) Steam generator
US4068627A (en) Steam generator with vertical tubesheets
KR100286518B1 (en) Separate Perfusion Spiral Steam Generator
US5386871A (en) Thermal energy storage and recovery system
US3084742A (en) Heat exchange apparatus
JPH076754B2 (en) Heat exchanger
US3216400A (en) Vertical nuclear boiler
US4445568A (en) Superheated steam generator
JPS63169405A (en) Steam generator
US4624304A (en) Expandable support for insertion into tube bundle
JPS63286601A (en) Steam generator
SU1617296A1 (en) Heat exchanger
RU98117938A (en) STEAM GENERATOR FOR INTEGRAL NUCLEAR REACTORS
US2796049A (en) Vapor generators
JP2714264B2 (en) Moisture separation heater
RU2135888C1 (en) Steam generator
JPH0358078B2 (en)
Nickerson et al. Nuclear steam generator tubesheet shield
JPS5855602A (en) Feedwater heater
JPH0317401A (en) Steam generator for liquid-metal cooled nuclear reactor
JPS62261996A (en) Coolant piping structure of pressurized water type reactor
JPS61186701A (en) Steam generator