JPS58219497A - Method of removing corrosion product of reactor - Google Patents

Method of removing corrosion product of reactor

Info

Publication number
JPS58219497A
JPS58219497A JP57102238A JP10223882A JPS58219497A JP S58219497 A JPS58219497 A JP S58219497A JP 57102238 A JP57102238 A JP 57102238A JP 10223882 A JP10223882 A JP 10223882A JP S58219497 A JPS58219497 A JP S58219497A
Authority
JP
Japan
Prior art keywords
reactor
corrosion products
water
nuclear reactor
pressure tube
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
JP57102238A
Other languages
Japanese (ja)
Inventor
佐々田 泰宏
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 JP57102238A priority Critical patent/JPS58219497A/en
Publication of JPS58219497A publication Critical patent/JPS58219497A/en
Pending legal-status Critical Current

Links

Classifications

    • Y—GENERAL 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
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y—GENERAL 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
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Landscapes

  • Preventing Corrosion Or Incrustation Of Metals (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】 本発明は原子炉の腐食生成物除去方法とその設備に係り
、特に沸騰軽水冷却圧力管型原子炉等に使用するに好適
な原子炉の腐食生成物除去方法とその設備に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a method for removing corrosion products from a nuclear reactor and its equipment, and in particular to a method for removing corrosion products from a nuclear reactor suitable for use in boiling light water cooled pressure tube reactors and the like. Regarding equipment.

沸騰軽水冷却圧力管型原子炉−次系の従来例を第1図に
示す。沸騰軽水冷却圧力管型原子炉は冷却材として中性
純水を使用する原子炉で、圧力管集合体1内の燃料集合
体2により加熱され沸騰した冷却水は蒸気ドラム3で気
水分離され、蒸気はタービン4へ、水は再循環ポンプ5
により圧力管集合体内へ戻される。タービンを駆動した
蒸気は復水器6内で凝縮し、復水ポンプ7、復水脱塩装
置8、低圧給水加熱器9、給水ポンプ10、高圧給水加
熱器11を経て蒸気ドラムに戻る。原子炉内を循環する
冷却水け、その一部が蒸気ドラムから再生熱交換器12
、非再生熱交換器13を経て原子炉冷却材浄化装置14
に導びかれ浄化された後、給水配管を経て蒸気ドラムに
戻される。
A conventional example of a boiling light water cooled pressure tube nuclear reactor system is shown in Figure 1. A boiling light water cooled pressure tube reactor is a nuclear reactor that uses neutral pure water as a coolant. Cooling water heated and boiled by a fuel assembly 2 in a pressure tube assembly 1 is separated into steam and water by a steam drum 3. , steam to turbine 4, water to recirculation pump 5
is returned into the pressure tube assembly. The steam that drove the turbine condenses in the condenser 6 and returns to the steam drum via a condensate pump 7, a condensate desalination device 8, a low-pressure feedwater heater 9, a feedwater pump 10, and a high-pressure feedwater heater 11. Cooling water circulating inside the reactor, a part of which is transferred from the steam drum to the regenerative heat exchanger 12
, the reactor coolant purification device 14 via the non-regenerative heat exchanger 13
After being purified, it is returned to the steam drum via water supply piping.

上記の如く原子炉−次系を循環する冷却水け、復水脱塩
装置及び原子炉冷却材浄化装置により浄化されているが
、主として復水系・給水系で発生した腐食生成物が原子
炉内に蓄積し、機器配管線着レベル増加の原因になって
いる。また、腐食生成物はその大部分が燃料集合体に付
着しているが、原子炉の停止時等にはく離脱落した腐食
生成物が圧力管集合体下部に堆積するとbう問題点があ
った。圧力管集合体下部には第2図に示すごとく着脱可
能なシールプラグ15が設けられ、シールエレメント1
6と圧力管集合体とのメタルタッチにより冷却水をシー
ルしているが、堆積した腐食生放物がシールプラグ着脱
の抵抗となり好ましくない。
As mentioned above, the reactor is purified by the cooling water drain, condensate desalination equipment, and reactor coolant purification equipment that circulate through the reactor subsystem, but corrosion products generated mainly in the condensate system and feed water system are inside the reactor. This causes an increase in the level of equipment piping wires. Furthermore, most of the corrosion products adhere to the fuel assembly, but when the reactor is shut down, the corrosion products that flake off and fall accumulate at the bottom of the pressure tube assembly, which is a problem. A removable seal plug 15 is provided at the bottom of the pressure tube assembly as shown in FIG.
Although the cooling water is sealed by the metal touch between the seal plug 6 and the pressure tube assembly, the accumulated corrosive substances create resistance to attaching and detaching the seal plug, which is not preferable.

本発明の目的は、燃料集合体に付着した腐食生成物がは
く離脱落により圧力管集合体下部に堆積し、シールプラ
グ着脱の抵抗になるのを防止できる原子炉の腐食生成物
除去方法とその設備を提供することにある。
An object of the present invention is to provide a method and equipment for removing corrosion products from a nuclear reactor that can prevent corrosion products adhering to a fuel assembly from being deposited at the bottom of a pressure pipe assembly due to flaking and falling and becoming a resistance to attaching and removing a seal plug. Our goal is to provide the following.

本発明は、燃料集合体に付着した腐食生成物かけ〈離脱
落して圧力管集合体下部に堆積するのを防止するため、
原子炉の停止時等に炉水のI)Hを約10以上とした循
環運転を行ない、燃料集合体に付着した腐食生成物を低
温部へ移行させ捕獲するようにしたものである。
The present invention prevents corrosion products adhering to the fuel assembly from falling off and depositing at the bottom of the pressure pipe assembly.
When the reactor is shut down, etc., a circulation operation is carried out with the I)H of the reactor water being about 10 or more, and the corrosion products adhering to the fuel assembly are transferred to a low-temperature part and captured.

本発明を沸騰軽水冷却圧力管型原子炉へ適用した場合の
一実施例を第3図に示す。
FIG. 3 shows an embodiment in which the present invention is applied to a boiling light water cooled pressure tube reactor.

原子炉内の腐食生成物は、炉水のI)Hが中性の場合高
温部に、pHが約10以上のアルカリ性の場合低温部に
付着しやすい特性を有することが知られている。沸騰水
冷却型原子炉では中性純水を使用するため腐食生成物の
大部分が高温の燃料集(3) 合体2表面に付着する。
It is known that corrosion products in a nuclear reactor tend to adhere to high-temperature parts when reactor water I)H is neutral, and to low-temperature parts when reactor water has an alkaline pH of about 10 or more. Since boiling water-cooled reactors use neutral pure water, most of the corrosion products adhere to the surface of the high-temperature fuel assembly (3).

第3図は燃料集合体表面に付着した腐食生成物を除去す
るため、原子炉冷却材浄化装置14にバイパスライン1
7を設け、本ラインにI)H調整剤注入・除去装置18
及びコールドトラップ19を設けたものである。通常運
転時中性の炉水を、間欠的に、または原子炉の停止時等
にI)Hを約10以上のアルカリ性にして循環運転を行
なえば、燃料集合体表面に付着した腐食生成物をコール
ドトラップに移行させ捕獲することができる。
Figure 3 shows a bypass line 1 connected to the reactor coolant purification system 14 in order to remove corrosion products adhering to the surface of the fuel assembly.
7 is installed, and an I)H regulator injection/removal device 18 is installed in the main line.
and a cold trap 19. If the reactor water, which is neutral during normal operation, is made intermittently or when the reactor is shut down to an alkaline I)H level of about 10 or more, corrosion products attached to the surface of the fuel assembly can be removed. It can be transferred to a cold trap and captured.

本発明の他の実施例を第4図に示す。Another embodiment of the invention is shown in FIG.

第4図は原子炉の停止時に崩壊熱を除去する余熱除去系
熱交換器20をコールドトラップとして使用し余熱除去
系ライン21にI)H調整剤注入・除去装置18を設け
たものである。余熱除去系は原子炉冷却材浄化系に比べ
て流量が大きいため、第3図の実施例に比べて本実施例
の方が腐食生成物の移行が短期間に行なえるという効果
がある。
In FIG. 4, a residual heat removal system heat exchanger 20 for removing decay heat when the reactor is shut down is used as a cold trap, and an I) H regulator injection/removal device 18 is provided in the residual heat removal system line 21. Since the residual heat removal system has a larger flow rate than the reactor coolant purification system, this embodiment has the effect that corrosion products can be transferred in a shorter period of time than the embodiment shown in FIG.

尚、第4図では余熱除去系熱交換器をコールドトラップ
とする例を示したが、第3図同様余熱除(4) 去来熱交換器にバイパスラインを設け、本ラインにコー
ルドトラップを設けることも可能である。
Note that Figure 4 shows an example in which the residual heat removal system heat exchanger is used as a cold trap, but as in Figure 3, a bypass line is provided in the residual heat removal (4) heat exchanger and a cold trap is provided in the main line. It is also possible.

本発明によれば、燃料集合体に付着した腐食生成物を減
少することができるので、はく離脱落した腐食生成物が
圧力管集合体下部に堆積し、シールプラグ着脱の抵抗に
なる等の問題を防止できる効果がある。また、燃料集合
体に付着した腐食生成物を減少することができるので、
機器配管の線量レベルを低減できる効果がある。
According to the present invention, it is possible to reduce the amount of corrosion products adhering to the fuel assembly, thereby preventing problems such as corrosion products that have flaked off and fallen down and accumulate at the bottom of the pressure pipe assembly, creating resistance to attaching and removing the seal plug. It has a preventive effect. Additionally, corrosion products adhering to the fuel assembly can be reduced.
It has the effect of reducing the dose level of equipment piping.

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

第1図は沸騰軽水冷却圧力管型原子炉−次系の従来例を
示す系統図、第2図は第1図の圧力管集合体下部の詳細
を示す構造図、第3図及び第4図は本発明を沸騰軽水冷
却圧力管型原子炉へ適用した場合の実施例を示す系統図
である。 1・・・圧力管集合体、2・・・燃料集合体、15・・
・シールプラグ、18・・・I)H調整剤注入・除去装
置、19第1 図
Figure 1 is a system diagram showing a conventional example of a boiling light water cooled pressure tube reactor system, Figure 2 is a structural diagram showing details of the lower part of the pressure tube assembly in Figure 1, Figures 3 and 4. 1 is a system diagram showing an embodiment in which the present invention is applied to a boiling light water cooled pressure tube nuclear reactor. 1... Pressure pipe assembly, 2... Fuel assembly, 15...
・Seal plug, 18...I) H regulator injection/removal device, 19 Fig. 1

Claims (1)

【特許請求の範囲】[Claims] 1、通常運転時中性水を使用する沸騰水冷却型原子炉に
おいて、定検時等に炉水のI)Hを約10以上のアルカ
リ性に調整して循還運転全行ない、燃料集合体等の高温
部に付着した腐食生成物をコールドトラップに移行させ
捕獲することを特徴とする原子炉の腐食生成物除去方法
。
1. In a boiling water-cooled nuclear reactor that uses neutral water during normal operation, the I)H of the reactor water is adjusted to an alkalinity of approximately 10 or more during regular inspections, etc., and all circulation operations are performed, and fuel assemblies, etc. A method for removing corrosion products from a nuclear reactor, the method comprising transferring corrosion products adhering to a high-temperature part of a nuclear reactor to a cold trap and capturing them.
JP57102238A 1982-06-16 1982-06-16 Method of removing corrosion product of reactor Pending JPS58219497A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57102238A JPS58219497A (en) 1982-06-16 1982-06-16 Method of removing corrosion product of reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57102238A JPS58219497A (en) 1982-06-16 1982-06-16 Method of removing corrosion product of reactor

Publications (1)

Publication Number Publication Date
JPS58219497A true JPS58219497A (en) 1983-12-20

Family

ID=14322051

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57102238A Pending JPS58219497A (en) 1982-06-16 1982-06-16 Method of removing corrosion product of reactor

Country Status (1)

Country Link
JP (1) JPS58219497A (en)

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