JPS58193495A - Condenser for bwr type reactor - Google Patents

Condenser for bwr type reactor

Info

Publication number
JPS58193495A
JPS58193495A JP57075399A JP7539982A JPS58193495A JP S58193495 A JPS58193495 A JP S58193495A JP 57075399 A JP57075399 A JP 57075399A JP 7539982 A JP7539982 A JP 7539982A JP S58193495 A JPS58193495 A JP S58193495A
Authority
JP
Japan
Prior art keywords
condenser
crud
tray
water
type reactor
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
JP57075399A
Other languages
Japanese (ja)
Inventor
五十嵐 裕夫
佐藤 善晃
勇作 西村
大角 克己
道好 山本
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 Engineering Co Ltd
Hitachi Ltd
Original Assignee
Hitachi Engineering Co Ltd
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 Engineering Co Ltd, Hitachi Ltd filed Critical Hitachi Engineering Co Ltd
Priority to JP57075399A priority Critical patent/JPS58193495A/en
Publication of JPS58193495A publication Critical patent/JPS58193495A/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

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】 本発明は沸騰水型原子力発電設備に係り、特にプラント
の放射能低減に好適な復水装置に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to boiling water nuclear power generation equipment, and particularly to a condensing device suitable for reducing radioactivity in a plant.

沸騰水散原子炉は蒸気でタービンを回転させた後、復水
器で蒸気を冷却凝縮させ、復水を浄化装置で不純物を取
り除き、再び給水ヒータで7Jo温し原子炉へ水を戻す
。この給水に配管等の腐食による腐食生成物(以下クラ
ッド)が不純物としであると原子炉内で放射化され、−
次系配管に放射性クラッドが付着し、プラントの放射線
々駿率乞上げることになる。このことから従来の研究に
より給水系においては、#l素注入することによりクラ
ッドの発生を著しく低減することに成功し、給水系にお
けるクラッドの発生は0.5 [)pb以下と無睨でき
る籠となっている。
In a boiling water reactor, steam is used to rotate a turbine, then the steam is cooled and condensed in a condenser, impurities are removed from the condensed water in a purification device, and the water is heated to 7 Jo again using a feed water heater and returned to the reactor. If corrosion products (hereinafter referred to as crud) due to corrosion of piping, etc. are present as impurities in this feed water, they will become radioactive in the reactor and -
Radioactive crud will adhere to the secondary system piping, increasing the radiation rate of the plant. Based on this, previous research has succeeded in significantly reducing the occurrence of crud in the water supply system by injecting #l element, and it is possible to reduce the occurrence of crud in the water supply system to less than 0.5[)pb. It becomes.

また復水浄化装置の上fil14クラッドの主発生源で
ある復水器の材aを大気脚★に強い耐候性鋼(例えば8
MA41A等)を採用することにより、浄化装置のクラ
ッド負荷を従来の1/3iKの109Pbまで低減して
いる。
In addition, the material a of the condenser, which is the main source of the upper fil14 crud of the condensate purification equipment, is made of weather-resistant steel (for example, 8
By adopting MA41A, etc.), the cladding load of the purifier is reduced to 109Pb, which is 1/3iK of the conventional one.

しかし、この場合でも復水浄化装置の性能は、50″4
〜70%であるためリークするクラッドは、3〜5 P
pbと1100MWe出力級1瑳子カグラ/トでは、年
間に原子炉へ持込まれるクラッドは120Kl〜200
Kfと多く、放射−々敏率も10011t/Hr超える
と予測されている。
However, even in this case, the performance of the condensate purification device is 50″4
~70% so the crud leaking is 3-5P
For pb and 1100 MWe power class 1 Ashi Kagura/to, the amount of crud brought into the reactor per year is 120Kl to 200Kl.
Kf, and the radiation sensitivity is predicted to exceed 10011t/Hr.

従って、現在の線層は、復水浄化装置の注11ヒを向上
させることと、更に復水器の腐食を低減することにかか
つている。特Ki者に関して、最近の研究により復水器
の材質として、耐候性鋼5MA41A等を採用している
が、耐候性鋼として、蒸気腐食にはその効果を埃わすが
、脱気された低浴存III素(〜7ppb)水には一般
の炭素鋼と同僚に極めて腐食しやすいことが判明した。
Therefore, current line layers are concerned with improving the performance of condensate purifiers and further reducing condenser corrosion. As for the special characteristics, recent research has shown that weathering steel such as 5MA41A has been adopted as the material for the condenser. It has been found that common carbon steels and co-workers are extremely susceptible to corrosion in water (~7 ppb).

令弟1図により従来の復水器を説明する。A conventional condenser will be explained with reference to Figure 1.

タービンをへた蒸気は蒸気ライン1により復水器2に入
り、冷却管3を通りぬける時に凝縮され水滴となり、ト
レイ4で脱気されてホットウェル5に流れて復水管6を
通って復水浄化装置へ行く。
The steam that has left the turbine enters the condenser 2 through the steam line 1, condenses into water droplets as it passes through the cooling pipe 3, is degassed in the tray 4, flows to the hot well 5, passes through the condensing pipe 6, and becomes condensed. Go to the purifier.

現在復水器2及びトレイ4及びホットウェル5の材質は
、すべて耐候性鋼を使用している。3水器2の胴体は4
気と接するが、トレイ4及びホットウェル5は脱気した
水と接している。従って、復水器で発生するクラッドは
トレイ4及びホントウェル5で発生していることになる
Currently, the condenser 2, tray 4, and hot well 5 are all made of weather-resistant steel. 3 The body of water vessel 2 is 4
The tray 4 and the hot well 5 are in contact with deaerated water. Therefore, the crud generated in the condenser is generated in the tray 4 and the real well 5.

第2図にトレイの詳細図を示す、このようにトレイは多
様のL型アングルで構成されており、クラッドの発生量
は極めて大きい。
FIG. 2 shows a detailed view of the tray. As shown, the tray is composed of various L-shaped angles, and the amount of crud generated is extremely large.

本発明の目的は、クラッド発生低減化のための復水器を
提供することにある。
An object of the present invention is to provide a condenser for reducing crud generation.

本発明は、耐候性鋼の特性として脱気水に均しては腐食
放出速度が大きいという試験結果から、復水器において
脱気水と接する箇所をステンレス鋼にすることにより、
原子炉へのクラッド持込みを低減するものである。
Based on test results showing that weathering steel has a high corrosion release rate compared to degassed water, the present invention has developed a system that uses stainless steel for the parts of the condenser that come into contact with degassed water.
This reduces the amount of crud carried into the reactor.

第3図に脱気水に対する相対に食放出速度を示す。これ
よりステンレス鋼の腐食放出速度は耐候性鋼に比べ約1
/2000以下である。
Figure 3 shows the food release rate relative to degassed water. From this, the corrosion release rate of stainless steel is about 1 compared to weathering steel.
/2000 or less.

以下本発明の一実施列を説明する。One embodiment of the present invention will be described below.

復水器の脱気水と接する箇所は、喧述の知く、トレイと
ホントウェルでろる。発生するクラッド量はその脱気水
の接する箇所の面積に依存することから、今10100
O・出力数の復水器でトレイとホットウェルを比較する
と、トレイの面積は750−とホットウェルの約3倍で
あり、トレイをステンレス鋼(例えば5US304)に
すればクラッドは着しく低減することになる。
As you know, the parts of the condenser that come into contact with deaerated water are the tray and the real well. Since the amount of crud generated depends on the area of the area in contact with the degassed water, the amount of crud generated is currently 10,100.
Comparing a tray and a hotwell in a condenser with an output number of O, the area of the tray is 750-, about three times that of a hotwell, and if the tray is made of stainless steel (for example, 5US304), the crud will be significantly reduced. It turns out.

そこでトレイをステンレス鋼にした場合の原子炉へのク
ラッド持込量を計算すると、復水浄化系の性能を’10
%とした場曾、耐候性鋼の半均160上 麺から804と約半分に低減できる。
Therefore, when calculating the amount of crud carried into the reactor when the tray is made of stainless steel, the performance of the condensate purification system is '10.
As a percentage, it can be reduced from half-uniform weathering steel noodles of 160 to 804, about half.

第4図はこの効果を示す一次系配管の表IjliIfi
Awk率とクラッド持込量の関係を解析した特性図であ
る。とれによると、将来線量率は170 ml(i/H
rから110mR/Hrと約35−低減できる。
Figure 4 is a table of primary system piping showing this effect.
It is a characteristic diagram which analyzed the relationship between Awk rate and the amount of crud brought in. According to Tore, the future dose rate will be 170 ml (i/H
r to 110 mR/Hr, which can be reduced by about 35-.

本発明によれば、復水器より発生するクラッドを低減す
ることにより、プラント放射−々量率を低、〈抑えるこ
とができるので、定倹時等の原子力発電所従業員の被曝
を少なくするに良好な効果がある。
According to the present invention, by reducing the crud generated from the condenser, the plant radiation rate can be kept low, thereby reducing the radiation exposure of nuclear power plant employees during regular periods, etc. has a good effect.

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

第1図は復水器の説明図、第2図はトレイの詳細図、第
3図は材質による腐食速度を示す特性図、第4図は給水
鉄持込量と配管表面線量率の相関を示す特性図である。 1・・・蒸気ライ/、2・・・復水器、4・・・トレイ
、5・・・茅3 目 茅4 目 チS永7う・/ドア4ジΣ」【
Figure 1 is an explanatory diagram of the condenser, Figure 2 is a detailed diagram of the tray, Figure 3 is a characteristic diagram showing the corrosion rate depending on the material, and Figure 4 is the correlation between the amount of iron brought into the feed water and the dose rate on the pipe surface. FIG. [

Claims (1)

【特許請求の範囲】[Claims] 1、原子炉より発生する蒸気を凝縮させる復水器におい
て、復水を脱気するトレイにオーステナイト系ステンレ
ス鋼を使用することを特徴とするBWR復水器。
1. A BWR condenser that condenses steam generated from a nuclear reactor and is characterized by using austenitic stainless steel for the tray that deaerates condensate.
JP57075399A 1982-05-07 1982-05-07 Condenser for bwr type reactor Pending JPS58193495A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57075399A JPS58193495A (en) 1982-05-07 1982-05-07 Condenser for bwr type reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57075399A JPS58193495A (en) 1982-05-07 1982-05-07 Condenser for bwr type reactor

Publications (1)

Publication Number Publication Date
JPS58193495A true JPS58193495A (en) 1983-11-11

Family

ID=13575056

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57075399A Pending JPS58193495A (en) 1982-05-07 1982-05-07 Condenser for bwr type reactor

Country Status (1)

Country Link
JP (1) JPS58193495A (en)

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