JP2003028315A - Manufacturing method of nuclear/thermal power plant valve device - Google Patents

Manufacturing method of nuclear/thermal power plant valve device

Info

Publication number
JP2003028315A
JP2003028315A JP2001220810A JP2001220810A JP2003028315A JP 2003028315 A JP2003028315 A JP 2003028315A JP 2001220810 A JP2001220810 A JP 2001220810A JP 2001220810 A JP2001220810 A JP 2001220810A JP 2003028315 A JP2003028315 A JP 2003028315A
Authority
JP
Japan
Prior art keywords
based alloy
eutectic carbide
valve
power plant
valve seat
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
JP2001220810A
Other languages
Japanese (ja)
Inventor
Mitsuo Chikazaki
充夫 近崎
Jiro Kuniya
治郎 国谷
Yoshihisa Kiyotoki
芳久 清時
Akira Sakamoto
坂本  明
Yoshiteru Chiba
良照 千葉
Shizuo Matsushita
静雄 松下
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 JP2001220810A priority Critical patent/JP2003028315A/en
Publication of JP2003028315A publication Critical patent/JP2003028315A/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

Abstract

PROBLEM TO BE SOLVED: To provide a valve having excellent corrosion/erosion resistance and maintainability by joining corrosion/wearing resisting alloy wherein eutectic carbide is discontinuously distributed to a sliding portions of various apparatus and valves by brazing, to improve the maintainability of thermal power plant and a nuclear power plant, and to provide the nuclear power plant being excellent in the safety of work and having a system for circulating primary cooling water. SOLUTION: In this valve and apparatus such as a nuclear power plant using the valve, eutectic carbide in alloy having a casting organization basic material portion and the eutectic carbide is formed in plural lumps or plural particles. corrosion/wearing resisting alloy wherein the eutectic carbide is discontinuously distributed is joined to a sliding portion.

Description

【発明の詳細な説明】Detailed Description of the Invention

【0001】[0001]

【発明の属する技術分野】本発明は、摺動部に耐食・耐
摩耗合金を接合した弁及びその弁を用いた原子力・火力
発電プラントに関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a valve in which a sliding portion is joined with a corrosion / wear resistant alloy and a nuclear / thermal power plant using the valve.

【0002】[0002]

【従来の技術】近年、タービン発電設備等では循環水の
水質調整のために循環水系統に過酸化水素水やヒドラジ
ン等の薬剤が注入されるようになり、該薬剤の注入点よ
り下流の溶存酸素量が増加し、その結果、弁の弁座面等
にエロージョン・かじり等による損傷が発生している。
2. Description of the Related Art In recent years, in turbine power generation facilities and the like, chemicals such as hydrogen peroxide solution and hydrazine have been injected into the circulating water system for adjusting the quality of the circulating water, and the chemicals dissolved downstream from the injection point of the chemicals. The amount of oxygen increases, and as a result, the valve seat surface of the valve is damaged by erosion and galling.

【0003】特開昭59−179283号公報には、C
r30〜45重量%、Ti3.0〜8.0重量%、Mo
0〜10重量%及び残部Niからなる弁座が弁体、弁箱
に拡散接合された弁について開示されている。
Japanese Unexamined Patent Publication No. 59-179283 discloses C
r30-45 wt%, Ti3.0-8.0 wt%, Mo
A valve in which a valve seat composed of 0 to 10% by weight and the balance Ni is diffusion-bonded to a valve body and a valve box is disclosed.

【0004】玉型弁、仕切り弁、バタフライバルブ等の
弁類は、実運転中の弁座付近での流体によるエロージョ
ン損傷を防止するため、或いは弁作動時のかじり防止の
ために、耐食・耐摩耗性に優れた高硬度のコバルト(C
o)基合金、ニッケル(Ni)基合金、鉄(Fe)基合
金等の表面溶着合金を弁の摺動部及び又は弁座部に肉盛
して用いている。
Valves such as a globe valve, a sluice valve, and a butterfly valve are corrosion and corrosion resistant in order to prevent erosion damage due to fluid near the valve seat during actual operation or to prevent galling during valve operation. High hardness cobalt (C
Surface-welding alloys such as o) base alloys, nickel (Ni) base alloys, and iron (Fe) base alloys are used by overlaying the sliding portion and / or the valve seat portion of the valve.

【0005】しかし、弁の摺動部、弁座部に肉盛してい
るコバルト(Co)基合金等の共晶炭化物が選択的に腐
食損傷する。循環水系統の流体は高温高圧、高速であり
前記の腐食損傷に続いて、鋳造組織の基地部(マトリッ
クス)が脱落し、エロージョンが発生する場合がある。
(火力原子力発電:30巻、No.5,67頁及び「機
械の損傷」:1982,No.2,90頁)。
However, eutectic carbides such as cobalt (Co) -based alloys which are built up on the sliding portion and the valve seat portion of the valve are selectively corroded and damaged. The fluid in the circulating water system has a high temperature, high pressure, and high speed, and following the above-mentioned corrosion damage, the matrix portion of the casting structure may fall off, and erosion may occur.
(Thermal power generation: Vol. 30, No. 5, p. 67 and "Damage to machinery": 1982, No. 2, p. 90).

【0006】この結果、弁の耐漏洩性能が低下したり、
弁の制御特性や作動特性が変化する等の不具合を生じ、
弁の分解点検頻度が増加し、プラントの保守性が低下す
る。
As a result, the leakage resistance of the valve is lowered,
Problems such as changes in valve control characteristics and operating characteristics occur,
The frequency of valve overhauls increases, and the maintainability of the plant decreases.

【0007】特に原子力発電設備においては、炉水と接
する摺動部及び炉内に冷却水を供給する系統設備の弁類
に上記事象が発生すると、これらの部位に肉盛されてい
る高硬度のCo基、Ni基或いはFe合金等は、腐食・
エロージョンによって脱落して系統中に混入する恐れが
ある。
Particularly in the nuclear power generation equipment, when the above-mentioned event occurs in the sliding parts in contact with the reactor water and the valves of the system equipment for supplying the cooling water into the reactor, the high hardness of the high hardness accumulated in these parts. Co base, Ni base, Fe alloy, etc.
There is a risk that it will fall off due to erosion and enter the system.

【0008】特開昭59−179283号公報では、C
r30〜45重量%、Ti3.0〜8.0重量%、Mo
0〜10重量%及び残部Niからなる弁座を弁体及び弁
箱に拡散接合することを提案している。また、特開昭6
0−86239号公報では、Cr30〜45重量%、A
l及びTiのうちの少なくともいずれか1種1.5〜
6.0重量%、Mo20重量%以下及び残部がNiから
なる弁座を弁体及び弁箱に拡散接合することを提案して
いる。
In Japanese Patent Laid-Open No. 59-179283, C
r30-45 wt%, Ti3.0-8.0 wt%, Mo
It is proposed that a valve seat composed of 0 to 10% by weight and the balance Ni be diffusion-bonded to the valve body and the valve box. In addition, JP-A-6
In 0-86239, Cr 30 to 45 wt%, A
at least one of l and Ti 1.5 to
It is proposed that a valve seat consisting of 6.0 wt%, Mo 20 wt% or less, and the balance being Ni is diffusion-bonded to the valve body and the valve box.

【0009】[0009]

【発明が解決しようとする課題】以上述べたように、従
来の鋳造組織基地部と網目状の共晶炭化物を有するCo
基、Ni基及びFe基肉盛金属は、耐食性・耐エロージ
ョン性が十分でない。本発明の目的は、これらのCo
基、Ni基及びFe基合金の共晶炭化物を非連続分布で
塊状及び粒状とした耐食・耐摩耗合金をろう付け接合に
より原子力及び火力発電プラントの弁の摺動部等に接合
し、耐食性・耐エロージョン性・保守性に優れた弁を提
供する。
As described above, Co having a conventional cast structure matrix and a network-like eutectic carbide is used.
Corrosion resistance and erosion resistance of base-based, Ni-based, and Fe-based overlay metals are not sufficient. The purpose of the present invention is to obtain these Co
Corrosion-resistant / wear-resistant alloy in which eutectic carbides of base, Ni-based and Fe-based alloys are discontinuously distributed in the form of lumps and particles is joined to the sliding parts of valves of nuclear power plants and thermal power plants by brazing for corrosion resistance / Provide a valve with excellent erosion resistance and maintainability.

【0010】本発明の目的は、原子力及び又は火力発電
プラントの設備に用いられている弁類の摺動部の耐食性
・耐エロージョン性を向上させることにより、原子力や
火力プラントの保守性の向上、特に作業の安全性に優れ
た一次冷却循環水系を有する原子力プラントを提供する
ことにある。
An object of the present invention is to improve the maintainability of nuclear power plants and thermal power plants by improving the corrosion resistance and erosion resistance of the sliding parts of valves used in the facilities of nuclear power plants and / or thermal power plants. In particular, it is to provide a nuclear power plant having a primary cooling circulating water system excellent in work safety.

【0011】[0011]

【課題を解決するための手段】本発明の要旨は次のとお
りである。
The gist of the present invention is as follows.

【0012】第一の手段は、鋳造組織基地部と共晶炭化
物を有する合金に鍛造又は圧延による塑性加工と加熱処
理を加えて前記共晶炭化物を非連続で塊状又は粒状に形
成して、塊状径又は粒径が30μm以下の共晶炭化物が
分布した耐食・耐摩耗コバルト基合金が摺動部にろう付
け接合されている弁である。コバルト基合金はたとえば
重量でC1〜3%、Si2%以下、Cr10〜32%、
W4〜15%、Fe3%以下、Ni3%以下、Mo5%
以下を含むものが好ましい。
The first means is to subject the alloy having the cast structure matrix and the eutectic carbide to plastic working by forging or rolling and heat treatment to form the eutectic carbide in a discontinuous lump or granular form to form a lump. It is a valve in which a corrosion-resistant / wear-resistant cobalt-based alloy in which a eutectic carbide having a diameter or particle size of 30 μm or less is distributed is brazed to a sliding portion. Cobalt-based alloys are, for example, C1-3% by weight, Si2% or less, Cr10-32%,
W4-15%, Fe3% or less, Ni3% or less, Mo5%
Those that include the following are preferred.

【0013】前記の鋳造組織基地部と共晶炭化物とを有
する合金に鍛造又は圧延による塑性加工と加熱処理を加
えて前記共晶炭化物を非連続分布で塊状又は粒状とした
耐食・耐摩耗合金がろう付け接合により摺動部に接合さ
れていることが好ましい。更に言えば、前記ろう付け接
合が母材より低融点のインサート材の箔とフラックス、
ろう付け用ペースト材等を組合わせ接合界面に挿入して
ろう付け接合を行うことが好ましい。なお、塊状径又は
粒状径を30μm以下にすることで、従来肉盛合金より
も良好な靭性を保つことができる。
A corrosion-resistant and wear-resistant alloy in which the eutectic carbide is lumped or granular in a discontinuous distribution by applying plastic working by forging or rolling and heat treatment to the alloy having the cast structure matrix and the eutectic carbide It is preferable that the sliding portion is joined by brazing. Further speaking, the brazing and joining of the foil and the flux of the insert material having a lower melting point than the base material,
It is preferable to perform a brazing joint by inserting a brazing paste material or the like into the combined joint interface. By setting the lump diameter or the grain diameter to 30 μm or less, it is possible to maintain better toughness than the conventional hardfacing alloy.

【0014】第二の手段は、原子炉の一次冷却水の循環
する系統内に弁を有する配管が設置された原子力プラン
トにおいて、該弁の摺動部が鋳造組織基地部と共晶炭化
物を有する合金中の前記共晶炭化物を非連続分布で塊状
又は粒状とした耐食・耐摩耗合金を有する原子力プラン
トである。前記の鋳造組織基地部と共晶炭化物とを有す
る合金に鍛造又は圧延による塑性加工と加熱処理を加え
て前記共晶炭化物を非連続分布で塊状又は粒状とした耐
食・耐摩耗合金がろう付け接合により摺動部に接合され
ていることが好ましい。
A second means is a nuclear power plant in which a pipe having a valve is installed in a system in which primary cooling water of a nuclear reactor circulates, and a sliding portion of the valve has a cast structure base portion and a eutectic carbide. A nuclear power plant having a corrosion-resistant and wear-resistant alloy in which the eutectic carbides in the alloy are discontinuously distributed in a lump or granular form. A corrosion-resistant and wear-resistant alloy is brazed to form an alloy having a cast structure matrix and eutectic carbide, which is plastically processed by forging or rolling and heat-treated to form the eutectic carbide in a lumped or granular form with a discontinuous distribution. Is preferably joined to the sliding portion.

【0015】第三の手段は、原子力プラントの原子炉の
炉水と接触する給水弁の摺動部非連続で塊状又は粒状に
共晶炭化物を形成したCo基、Ni基及びFe基耐食・
耐摩耗合金がろう付け接合により接合されている原子力
発電プラントである。
A third means is a Co-based, Ni-based, and Fe-based corrosion-resistant corrosion-resistant Co-based alloy in which a eutectic carbide is formed in a lump or a grain in a discontinuous sliding portion of a feed valve which comes into contact with reactor water of a nuclear power plant.
A nuclear power plant in which wear-resistant alloys are joined by brazing.

【0016】第四の手段は、原子力プラントの原子炉の
炉水と接触する給水弁の摺動部に非連続で塊状又は粒状
に共晶炭化物を形成したCo基、Ni基及びFe基耐食
・耐摩耗合金が摩擦圧接により接合されている原子力発
電プラントである。
A fourth means is a Co-based, Ni-based and Fe-based corrosion-resistant corrosion-resistant Co-based, Ni-based and Fe-based alloy which forms a lumpy or granular eutectic carbide in the sliding portion of the feed valve which comes into contact with the reactor water of the nuclear power plant. A nuclear power plant in which wear-resistant alloys are joined by friction welding.

【0017】[0017]

【発明の実施の形態】本発明は、機器の摺動部・弁の弁
座部等の耐摩耗材として使用されているCo基合金、N
i基合金、Fe基合金等の表面溶着金属を構成する鋳造
組織の基地部と共晶炭化物のうち、網目状に連続して分
布する共晶炭化物を塊状又は粒状として非連続化した耐
食・耐摩耗合金を、各種機器及び弁類の摺動部にろう付
け接合又は摩擦圧接により接合し、機器及び弁の摺動部
の摩擦抵抗の増加を抑制し、特に弁にあっては弁座面等
の荒れによる耐漏えい性能の低下を抑制したことを特徴
とする機器及び弁に関する。
BEST MODE FOR CARRYING OUT THE INVENTION The present invention is a Co-based alloy, N, which is used as a wear resistant material for sliding parts of equipment, valve seats of valves and the like.
Of the matrix of the casting structure and the eutectic carbides that form the surface-deposited metal such as i-based alloys and Fe-based alloys, the eutectic carbides that are continuously distributed in the form of a mesh are discontinuous in the form of lumps or particles to prevent corrosion and resistance. The wear alloy is joined to the sliding parts of various devices and valves by brazing or friction welding to suppress the increase of the friction resistance of the sliding parts of the devices and valves. The present invention relates to a device and a valve which are characterized in that the deterioration of the leakproof performance due to the roughening of the material is suppressed.

【0018】網目状に連続して分布する共晶炭化物を塊
状又は粒状として非連続化するには、例えば肉盛用の表
面溶着合金に鍛造・圧延等の塑性加工と加熱処理(焼
鈍)を行う方法があるが、これに限定するものではな
い。
In order to discontinue the eutectic carbide continuously distributed in the form of a mesh in the form of lumps or particles, for example, the surface welding alloy for overlay welding is subjected to plastic working such as forging and rolling and heat treatment (annealing). However, the method is not limited to this.

【0019】共晶炭化物が不連続化した耐食・耐摩耗合
金の摺動部への接合はろう付け接合によって実現でき
る。ろう付け接合では、母材(非接合材)よりも低融点
のインサート材(ろう材)を接合界面に挿入し、接合時
にインサート材が溶融し、母材と接合材の間で化学結合
力と物理的粘着力を利用してろう付け接合が可能であ
る。接合による変形を少なく抑えることができる。ま
た、接合面の機械加工仕上げ精度は30μm程度でろう
付け接合が可能である。
The joining of the corrosion-resistant and wear-resistant alloy having the discontinuous eutectic carbide to the sliding portion can be realized by brazing. In brazing, an insert material (brazing material) with a melting point lower than that of the base material (non-bonding material) is inserted into the joint interface, the insert material melts at the time of joining, and the chemical bonding force between the base material and the bonding material increases. Brazing and joining can be performed by utilizing physical adhesive strength. The deformation due to joining can be suppressed to a small level. In addition, brazing can be performed with a machined finish accuracy of the joint surface of about 30 μm.

【0020】本発明によれば、通常状態では共晶炭化物
が網目状に連続している肉盛用のCo基、Ni基、Fe
基等の溶着合金について、共晶炭化物を塊状又は粒状に
変化させることで、非連続な共晶炭化物を有する耐食・
耐摩耗合金となる。この耐食・耐摩耗合金を弁及び機器
の摺動部にろう付け接合することにより、循環水系統に
過酸化水素やヒドラジン等の薬剤が注入されることによ
り溶存酸素量が増加し、その系統に存在する弁及び機器
の摺動部の共晶炭化物の腐食損傷を抑制し、同時に摺動
部の摩擦抵抗の増加や弁座面等の荒れによる耐漏えい性
能の低下も抑制し、保守性に優れた弁や機器を提供でき
る。又、本発明によれば、鍛造又は圧延等の塑性加工と
加熱処理(焼鈍)を施した板材、棒材から切り出した塊
状又は粒状の共晶炭化物を有するCo基、Ni基、Fe
基等の耐食・耐摩耗合金を弁座等にろう付け接合するこ
とで、溶存酸素がもたらす弁座等の腐食損傷やエロージ
ョン損傷を低減した安全弁、仕切り弁、玉型弁等を提供
できる。
According to the present invention, in a normal state, eutectic carbides are continuous in a network and are used for overlaying Co group, Ni group, Fe.
Corrosion resistance of discontinuous eutectic carbides by changing the eutectic carbides into agglomerates or granules for welded alloys such as bases
It becomes a wear resistant alloy. By brazing and joining this corrosion- and wear-resistant alloy to the sliding parts of valves and equipment, the amount of dissolved oxygen is increased by injecting chemicals such as hydrogen peroxide and hydrazine into the circulating water system, Suppresses the corrosion damage of existing eutectic carbides in the sliding parts of valves and equipment, and at the same time suppresses the increase in the friction resistance of sliding parts and the deterioration of the leakage resistance due to the roughness of the valve seat surface, etc. Valve and equipment can be provided. Further, according to the present invention, a plate material that has been subjected to plastic working such as forging or rolling and heat treatment (annealing), a Co-based material having a lump or granular eutectic carbide cut out from a bar material, a Ni-based material, and Fe.
By brazing a corrosion resistant / wear resistant alloy such as a base to a valve seat or the like, it is possible to provide a safety valve, a sluice valve, a sphere valve or the like in which corrosion damage or erosion damage of the valve seat or the like caused by dissolved oxygen is reduced.

【0021】更に、本発明によれば、原子力発電設備の
弁類に使用されているCo基合金の腐食・エロージョン
・摩耗等によるCoの飛散・拡散を抑制でき、保守性に
優れた原子力発電プラントを提供できる。
Further, according to the present invention, it is possible to suppress the scattering and diffusion of Co due to the corrosion, erosion, wear, etc. of the Co-based alloy used in the valves of nuclear power generation facilities, and the nuclear power plant with excellent maintainability. Can be provided.

【0022】従来、弁の摺動部、弁座部及び機器の摺動
部には、エロージョン防止、かじり防止のために、たと
えば高硬度の1.3重量%C、−27.7重量%Cr、
−4.9重量%Wを含むCo基合金等が表面溶着合金と
して用いられている。これらはガス溶接、PTA(Plas
ma Transfer Arc)等の電弧溶接等によって肉盛され
る。しかし、上記のCo基合金では、Cr、Cを主成分
とする共晶炭化物がCoを主成分とする鋳造組織の基地
部(マトリックス)に網目状に連続しており、その腐食
・エロージョンは溶存酸素により網目状の共晶炭化物が
腐食することで鋳造組織基地部が脱落し易くなり進行す
る。
Conventionally, in order to prevent erosion and galling, for example, high hardness of 1.3% by weight C, -27.7% by weight Cr is applied to the sliding portion of the valve, the valve seat portion and the sliding portion of the equipment. ,
A Co-based alloy containing -4.9 wt% W is used as the surface welding alloy. These are gas welding, PTA (Plas
It is built up by electric arc welding such as ma transfer arc). However, in the above Co-based alloy, the eutectic carbides containing Cr and C as the main components are continuous in a matrix form in the matrix of the cast structure containing Co as the main component, and their corrosion and erosion are dissolved. Oxygen corrodes the network-shaped eutectic carbide, and the matrix portion of the cast structure is likely to drop off and progresses.

【0023】本発明のCo基耐食・耐摩耗合金では、鍛
造・圧延等の塑性加工とその後の加熱処理(焼鈍)を行
う工程、或いは高温で熱間鍛造・熱間圧延を行う工程を
加えることにより、共晶炭化物は鋳造組織基地部中に塊
状又は粒状に非連続に分布しており、溶存酸素による炭
化物の腐食損傷は溶存酸素に接する面の炭化物にのみに
限られ、鋳造組織基地部の脱落は抑制される。
In the Co-based corrosion resistant and wear resistant alloy of the present invention, a step of performing plastic working such as forging and rolling and subsequent heat treatment (annealing) or a step of hot forging and hot rolling at high temperature is added. Therefore, the eutectic carbides are discontinuously distributed in the cast structure matrix in the form of lumps or grains, and the corrosion damage of the carbide due to dissolved oxygen is limited to only the carbide on the surface in contact with the dissolved oxygen. Dropout is suppressed.

【0024】上記効果は、網目状の共晶炭化物あるいは
塊状又は粒状の共晶炭化物を有するCo−1.3%C−
27.7%Cr−4.9%W合金の粒界腐食試験(スト
ラウス試験:JIS G0575)等により確認でき
る。共晶炭化物が網目状の場合に比較して、塊状又は粒
状の場合にはストラウス試験における腐食深さが1/3
00程度に抑制される。
The above effect is obtained by Co-1.3% C- having a eutectic carbide in the form of a mesh or a eutectic carbide in the form of lumps or particles.
It can be confirmed by a grain boundary corrosion test (Strauss test: JIS G0575) of a 27.7% Cr-4.9% W alloy. When the eutectic carbide is in the form of a mesh, the corrosion depth in the Strauss test is 1/3 when it is in the form of lumps or grains.
It is suppressed to about 00.

【0025】本発明が適用される弁は、特に限定される
ものではなく、各種の安全弁、仕切り弁、玉型弁等に適
用可能である。 (実施例1)本実施例では、1050〜1150℃での
熱間鍛造及び同じ温度での熱間圧延によって粒径30μ
m以下の塊状又は粒状の炭化物を形成した高硬度の1.
1重量%C、27.7重量%Cr、4.5重量%Wを含
む耐食・耐摩耗Co基合金をろう付け接合によって、溶
存酸素雰囲気下で使用する仕切り弁の弁座に接合した。
The valve to which the present invention is applied is not particularly limited and can be applied to various safety valves, sluice valves, lens valves and the like. (Example 1) In this example, a grain size of 30 μ was obtained by hot forging at 1050 to 1150 ° C. and hot rolling at the same temperature.
1. With high hardness, which formed lumpy or granular carbides of m or less.
A corrosion-resistant and wear-resistant Co-based alloy containing 1 wt% C, 27.7 wt% Cr, and 4.5 wt% W was joined by brazing to the valve seat of a sluice valve used in a dissolved oxygen atmosphere.

【0026】仕切り弁の構造を図1〜図3に示す。図1
は本実施例による仕切り弁の断面図を示している。図2
は弁体の拡大図を示し、図3は弁箱の拡大図を示してい
る。図1はSCPH2(S25C相当品)の鋳物からな
る仕切り弁の縦断面図である。まず、図2の弁体50へ
共晶炭化物を非連続で塊状又は粒状にしたリング100
aを接合した。図3は弁箱の拡大図を示す。弁箱511
へ共晶炭化物を非連続分布した塊状及び粒状にしたリン
グ100bを接合した。接合面上にフラックスを塗布し
たインサート材を置き、該インサート材の上に共晶炭化
物を塊状又は粒状とした厚さ6mmのリング板形状の前
述の耐食・耐摩耗Co基合金を置いてろう付け接合を行
った。上記インサート材は厚さ0.5mmで、その固相
線温度及び液相線温度はそれぞれ約650℃及び690
℃である。ろう付け接合条件は、ろう付け接合温度:8
00℃、保持時間:1時間、真空度:2×10-4Tor
r、加圧力:100g/cm2とした。
The structure of the sluice valve is shown in FIGS. Figure 1
Shows a sectional view of a sluice valve according to the present embodiment. Figure 2
Shows an enlarged view of the valve body, and FIG. 3 shows an enlarged view of the valve box. FIG. 1 is a vertical cross-sectional view of a sluice valve made of a cast of SCPH2 (S25C equivalent product). First, the ring 100 in which the eutectic carbide is discontinuously lumped or granulated to the valve body 50 of FIG.
a was joined. FIG. 3 shows an enlarged view of the valve box. Valve box 511
A ring 100b in which a eutectic carbide was discontinuously distributed and which was in the form of lumps and granules was joined. A flux-coated insert material is placed on the joint surface, and the above-mentioned corrosion-resistant and wear-resistant Co-based alloy in the form of a ring plate having a thickness of 6 mm in which eutectic carbide is lumped or granular is brazed on the insert material. Joined. The insert material has a thickness of 0.5 mm, and its solidus temperature and liquidus temperature are about 650 ° C. and 690 ° C., respectively.
℃. The brazing and joining conditions are brazing and joining temperature: 8
00 ° C, holding time: 1 hour, vacuum degree: 2 × 10 -4 Tor
r, applied pressure: 100 g / cm 2 .

【0027】ろう付け接合後に接合界面の断面観察を実
施したところ、ボイド等の接合欠陥はほとんど認められ
ず、良好なろう付け接合状態を示した。また、本実施例
で製作した仕切り弁は溶存酸素による共晶炭化物の連続
的な腐食発生が抑制され、鋳造組織の基材部の脱落が抑
制されるために、弁座1の腐食・エロージョンの進行が
抑止され、耐漏えい性能の低下が防止される。 (実施例2)本実施例では、1050℃〜1100℃で
の熱間鍛造によって共晶炭化物を塊状又は粒状とした高
硬度の1.1重量%C−29.7重量%Cr−4.5重
量%Wを含む耐食・耐摩耗Co基合金をろう付け接合に
よって、溶存酸素雰囲気下で使用する逆仕弁に接合し
た。図4は本実施例による逆止弁の断面図を示してい
る。接合条件は:800℃で大気中、保持時間:1時
間、加圧力:100g/cm 2とした。ろう付け接合界
面の断面観察を実施したところ、ボイド等の接合欠陥は
ほどんと認められず、良好な接合状態を示した。また、
本実施例で製作した逆止弁は溶存酸素による共晶炭化物
の腐食発生が抑制され、鋳造組織の基材部の脱落が抑制
されるために、弁座面1a及び1bの腐食が抑止され、
耐漏えい性能の低下が防止される。
After the brazing and welding, the cross-section of the joint interface was observed.
When applied, almost no bonding defects such as voids were observed.
However, a good brazed joint state was exhibited. In addition, this embodiment
The sluice valve manufactured by
Of the base material in the casting structure is suppressed
Therefore, the corrosion of the valve seat 1 and the progress of erosion are suppressed.
As a result, the leakage resistance is prevented from deteriorating. (Example 2) In this example, at 1050 ° C to 1100 ° C
Eutectic carbides were made into lumps or granules by hot forging
1.1% by weight of hardness C-29.7% by weight Cr-4.5 weight
Corrosion-resistant / wear-resistant Co-based alloy containing amount% W for brazing
Therefore, attach it to a reverse valve that is used in a dissolved oxygen atmosphere.
It was FIG. 4 shows a cross-sectional view of the check valve according to this embodiment.
It Bonding conditions: 800 ° C in air, holding time: 1 hour
Pressure, 100 g / cm 2And Brazing joint
When the cross section of the surface was observed, junction defects such as voids
It was not observed so much and showed a good bonding state. Also,
The check valve manufactured in this example is a eutectic carbide due to dissolved oxygen.
Corrosion is suppressed and the base material of the casting structure is prevented from falling off.
Therefore, corrosion of the valve seat surfaces 1a and 1b is suppressed,
The deterioration of the leakage resistance performance is prevented.

【0028】なお、上記実施例1及び2ではインサート
材へフラックスを塗布しCo基合金をろう付け接合した
が、Ni基合金、Fe基合金にも同様に適用可能であ
る。 (実施例3)本実施例では、1050〜1150℃での
熱間鍛造及び同じ温度での熱間圧延によって粒径30μ
m以下の塊状又は粒状の炭化物を形成した高硬度の1.
1重量%C、29.7重量%Cr、4.5重量%Wを含
む耐食・耐摩耗Co基合金を摩擦圧接を用い、溶存酸素
雰囲気下で制御系に使用する小型仕切り弁の弁座に接合
した。摩擦圧接の接合条件として、固定側がSCPH2
(S25C相当品)弁体、回転側がリング形状の耐食・
耐摩耗Co基合金、摩擦圧力は5〜10kg/mm2
アプセット圧力は10〜20kg/mm2、摩擦時間は
10〜20S、回転数2500〜3000rpmで直径
50mmの仕切り弁体を製作した。また、上記の条件で
弁座側も製作した。
Although the flux is applied to the insert material and the Co-based alloy is brazed and joined in the above-mentioned Examples 1 and 2, the Ni-based alloy and the Fe-based alloy can be similarly applied. (Example 3) In this example, a grain size of 30 μ was obtained by hot forging at 1050 to 1150 ° C. and hot rolling at the same temperature.
1. With high hardness, which formed lumpy or granular carbides of m or less.
Corrosion- and wear-resistant Co-based alloy containing 1 wt% C, 29.7 wt% Cr, and 4.5 wt% W is used for the valve seat of a small sluice valve used in a control system in a dissolved oxygen atmosphere by friction welding. Joined. As a welding condition for friction welding, the fixed side is SCPH2.
(S25C equivalent product) Corrosion resistance of valve body and ring side on the rotating side
Wear-resistant Co-based alloy, friction pressure 5-10 kg / mm 2 ,
A partition valve body having an upset pressure of 10 to 20 kg / mm 2 , a friction time of 10 to 20 S, a rotation speed of 2500 to 3000 rpm, and a diameter of 50 mm was manufactured. The valve seat side was also manufactured under the above conditions.

【0029】摩擦圧接後に接合界面の断面観察を実施し
た結果、接合不良、割れ、溶融部等の接合欠陥は認めら
れず、良好な摩擦圧接接合状態を示した。また、本実施
例で製作した仕切り弁は溶存酸素による共晶炭化物の連
続的な腐食発生が抑制され、鋳造組織の基材部の脱落が
抑制されるために、弁座1の腐食・エロージョンの進行
が抑制され、耐漏えい性能の低下が防止される。
As a result of observing the cross section of the joining interface after friction welding, no joining defects such as joining defects, cracks, and fused parts were observed, and a good friction welding joining state was shown. Further, since the sluice valve manufactured in this example suppresses the continuous corrosion generation of the eutectic carbide due to the dissolved oxygen and the falling of the base material portion of the cast structure, the corrosion / erosion of the valve seat 1 is suppressed. The progress is suppressed, and the deterioration of the leakproof performance is prevented.

【0030】図5は本発明の弁を一次冷却水の循環する
系統設備に用いた原子力プラントの配管系統図の例であ
る。
FIG. 5 is an example of a piping system diagram of a nuclear power plant in which the valve of the present invention is used for system equipment for circulating primary cooling water.

【0031】本発明に係わる弁は、一次冷却水の循環す
る系統設備に非常に多く存在しているので、図示は省略
する。
The valve according to the present invention is present in a large number in the system equipment in which the primary cooling water circulates, and therefore the illustration is omitted.

【0032】図5に示す原子力プラントでは、一次冷却
水は原子炉圧力容器14で熱せられ高温高圧蒸気となっ
て主蒸気管15を通って高圧タービン18に導入され
る。次いで、高圧タービン18から排出蒸気は低圧ター
ビン19に導入され発電機20を駆動する。高圧タービ
ン18及び低圧タービン19からの排出蒸気は主覆水器
10を経た後、本発明の多くの弁を有する給水系6によ
り給水ポンプ30、高圧給水加熱器31を経て給水管9
を通って原子炉圧力容器14に往復水する。
In the nuclear power plant shown in FIG. 5, the primary cooling water is heated in the reactor pressure vessel 14 and becomes high-temperature high-pressure steam, which is introduced into the high-pressure turbine 18 through the main steam pipe 15. Next, the exhaust steam from the high-pressure turbine 18 is introduced into the low-pressure turbine 19 to drive the generator 20. Exhaust steam from the high-pressure turbine 18 and the low-pressure turbine 19 passes through the main water cover 10, and then through the water supply system 6 having many valves of the present invention, the water supply pump 30, the high-pressure water supply heater 31, and the water supply pipe 9.
Water is reciprocated to and from the reactor pressure vessel 14 through.

【0033】本発明は、原子力発電プラント内の機器や
弁の寿命の延命に効果があり、プラント内の作業員の放
射線被曝を低減することができる。
The present invention is effective in extending the life of the equipment and valves in a nuclear power plant, and can reduce the radiation exposure of workers in the plant.

【0034】また、本発明の方法は上記仕切り弁や逆止
弁のみならず、安全弁、玉型弁等の弁座部等の摺動部に
適用することで、耐漏えい性能の低下、制御性・作動性
能の低下を抑制する効果がある。
Further, the method of the present invention is applied not only to the sluice valve and the check valve described above but also to sliding parts such as valve seats of safety valves, target valves, etc., to reduce the leakage resistance performance and controllability. -It has the effect of suppressing the deterioration of operating performance.

【0035】以上の弁を組合わせて使用することで、タ
ービン発電設備等のプラント設備で行われている。水質
調整の目的の過酸化水素水の注入等による溶存酸素の影
響による弁類の弁座等の摺動部の腐食・エロージョンを
抑制でき、タービン発電設備等のプラント設備の安全性
向上に効果がある。
By using the above valves in combination, this is performed in plant equipment such as turbine power generation equipment. Corrosion and erosion of sliding parts such as valve seats of valves due to the influence of dissolved oxygen due to injection of hydrogen peroxide water for the purpose of water quality control can be suppressed, and it is effective in improving the safety of plant equipment such as turbine power generation equipment. is there.

【0036】特に、原子力発電設備においては一次冷却
水の接する摺動部及び炉内に冷却水を供給する系統設備
の弁の弁座・ケージ等のCo基合金の共晶炭化物の腐食
脱落とそれに伴う、Coの系統内への流出・拡散を抑制
すると共に、共晶炭化物の腐食脱落によって耐エロージ
ョン性能の低下したCoを主成分とする鋳造組織の基地
部の脱落を抑制した原子力発電プラントを提供する。
In particular, in nuclear power generation equipment, the eutectic carbides of Co-based alloys such as valve seats and cages of valves of system equipment for supplying cooling water to the sliding parts in contact with the primary cooling water and corrosion of the eutectic carbides are removed. Providing a nuclear power plant that suppresses the outflow and diffusion of Co into the system, and also suppresses the removal of the base of the casting structure mainly composed of Co, which has reduced erosion resistance due to the corrosion loss of eutectic carbides. To do.

【0037】[0037]

【発明の効果】以上のように、本発明の機器及び弁によ
れば、流体中の溶存酸素による共晶炭化物の腐食損傷に
伴う弁の摺動部又は弁座部の荒れが少なく、摺動部や弁
座部での摩擦抵抗の増加抑制や弁座部での漏えいの防止
を確実に維持できる。
As described above, according to the apparatus and valve of the present invention, the sliding portion or valve seat portion of the valve is less rough due to the corrosion damage of the eutectic carbide due to the dissolved oxygen in the fluid, and the sliding It is possible to reliably maintain the increase in frictional resistance at the valve seat and the valve seat, and the prevention of leakage at the valve seat.

【0038】また、本発明の原子力発電プラントは、そ
のプラント内の機器や弁の寿命が延命される上、プラン
ト内の作業員の放射線被曝を低減することができる。
Further, the nuclear power plant of the present invention can prolong the life of the equipment and valves in the plant, and can reduce the radiation exposure of workers in the plant.

【0039】[0039]

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

【図1】仕切り弁の縦断面図である。FIG. 1 is a vertical cross-sectional view of a sluice valve.

【図2】仕切り弁の弁体部の拡大図である。FIG. 2 is an enlarged view of a valve body portion of a gate valve.

【図3】仕切り弁の弁箱弁座部の拡大図である。FIG. 3 is an enlarged view of a valve box valve seat portion of the sluice valve.

【図4】逆止弁の縦断面図である。FIG. 4 is a vertical sectional view of a check valve.

【図5】本発明の弁を給水系に用いた原子力プラントの
配管系統図である。
FIG. 5 is a piping system diagram of a nuclear power plant using the valve of the present invention for a water supply system.

【符号の説明】[Explanation of symbols]

50…弁体、100a…炭化物を塊状、粒状としたCo
基合金リング、511…弁箱弁座、100b…塊状、粒
状としたCo基合金リング、5…冷却水浄化系熱交換
器、6…給水弁系、7…給水加熱器、8…再循環系配
管、9…給水管、10…主復水器、11…SLCタン
ク、12…SLCポンプ、13…格納容器、14…原子
炉圧力容器、15…主蒸気管、16…給水管、17…湿
分分析器、18…高圧タービン、19…低圧タービン、
20…発電機、21…主変圧器、22…排気筒、23…
オフガス処理系、24…空気抽出器、25…低圧復水ポ
ンプ、26…グランド蒸気復水器、27…復水貯蔵槽、
28…復水ろ過装置、29…復水脱塩装置、30…給水
ポンプ、31…高圧給水加熱器、32…制御棒駆動系、
33、36…熱交換器、34…ろ過脱塩器、35…原子
炉隔離時冷却系。
50 ... Valve body, 100a ... Co that is made of lumps and particles of carbide
Base alloy ring, 511 ... Valve box valve seat, 100b ... Cobalt alloy ring in block shape, 5 ... Cooling water purification system heat exchanger, 6 ... Water supply valve system, 7 ... Water supply heater, 8 ... Recirculation system Piping, 9 ... Water supply pipe, 10 ... Main condenser, 11 ... SLC tank, 12 ... SLC pump, 13 ... Containment vessel, 14 ... Reactor pressure vessel, 15 ... Main steam pipe, 16 ... Water supply pipe, 17 ... Wet Minute analyzer, 18 ... high-pressure turbine, 19 ... low-pressure turbine,
20 ... Generator, 21 ... Main transformer, 22 ... Exhaust pipe, 23 ...
Off-gas treatment system, 24 ... Air extractor, 25 ... Low-pressure condensate pump, 26 ... Grand steam condenser, 27 ... Condensate storage tank,
28 ... Condensate filtration device, 29 ... Condensate desalination device, 30 ... Water supply pump, 31 ... High pressure water heater, 32 ... Control rod drive system,
33, 36 ... Heat exchanger, 34 ... Filtration demineralizer, 35 ... Reactor isolation cooling system.

───────────────────────────────────────────────────── フロントページの続き (72)発明者 清時 芳久 茨城県日立市幸町三丁目1番1号 株式会 社日立製作所原子力事業部内 (72)発明者 坂本 明 茨城県日立市幸町三丁目1番1号 株式会 社日立製作所原子力事業部内 (72)発明者 千葉 良照 茨城県日立市弁天町三丁目10番2号 日立 協和エンジニアリング株式会社内 (72)発明者 松下 静雄 茨城県日立市弁天町三丁目10番2号 日立 協和エンジニアリング株式会社内 Fターム(参考) 3H052 AA02 BA23 CA38 CA39 CB38 CB39 EA10 3H054 AA01 BB13 CA39 CA40 CC08 CC09 GG10    ─────────────────────────────────────────────────── ─── Continued front page    (72) Inventor Yoshihisa Kiyoshi             3-1-1 Sachimachi, Hitachi City, Ibaraki Prefecture Stock Association             Hitachi, Ltd. Nuclear Business Division (72) Inventor Akira Sakamoto             3-1-1 Sachimachi, Hitachi City, Ibaraki Prefecture Stock Association             Hitachi, Ltd. Nuclear Business Division (72) Inventor Yoshiteru Chiba             Hitachi, 3-10-3 Bentencho, Hitachi City, Ibaraki Prefecture             Kyowa Engineering Co., Ltd. (72) Inventor Shizuo Matsushita             Hitachi, 3-10-3 Bentencho, Hitachi City, Ibaraki Prefecture             Kyowa Engineering Co., Ltd. F-term (reference) 3H052 AA02 BA23 CA38 CA39 CB38                       CB39 EA10                 3H054 AA01 BB13 CA39 CA40 CC08                       CC09 GG10

Claims (7)

【特許請求の範囲】[Claims] 【請求項1】 鍛造又は圧延金属組織部に共晶炭化物を
有し、該共晶炭化物の形状が非連続的に塊状又は粒状で
あるコバルト基合金、ニッケル基合金又は鉄基合金が摺
動部及び又は弁座部にろう付け接合されていることを特
徴とする原子力・火力発電プラント用弁装置の製造方
法。
1. A sliding portion is a cobalt-based alloy, a nickel-based alloy or an iron-based alloy having a eutectic carbide in a forged or rolled metallographic structure, and the shape of the eutectic carbide is discontinuously lumpy or granular. And / or a valve seat portion is brazed to the valve seat portion, and a method for manufacturing a valve device for a nuclear / thermal power plant.
【請求項2】 鍛造又は圧延金属組織部に共晶炭化物を
有し、該共晶炭化物の形状が非連続で30μm以下の塊
状又は粒状であるコバルト基合金、ニッケル基合金又は
鉄基合金が摺動部及び又は弁座部にろう付け接合されて
いることを特徴とする原子力・火力発電プラント用弁装
置の製造方法。
2. A cobalt-based alloy, a nickel-based alloy or an iron-based alloy having a eutectic carbide in a forged or rolled metallographic structure portion, the shape of the eutectic carbide being discontinuous and in the form of lumps or particles of 30 μm or less. A method for manufacturing a valve device for a nuclear / thermal power plant, which is brazed to a moving part and / or a valve seat part.
【請求項3】 鍛造又は圧延金属組織に共晶炭化物を有
し、該共晶炭化物の形状が非連続で30μm以下の塊状
又は粒状であるコバルト基合金、ニッケル基合金又は鉄
基合金を摺動部及び又は弁座部にろう付け接合する場
合、前記摺動部材の固相線温度より50℃低い温度から
300℃までの温度範囲でろう付け接合されていること
を特徴とする原子力・火力発電プラント用弁装置の製造
方法。
3. Sliding a cobalt-based alloy, a nickel-based alloy or an iron-based alloy having a eutectic carbide in the forged or rolled metal structure, and the shape of the eutectic carbide is discontinuous and is a lump or granularity of 30 μm or less. And / or valve seat portion, which is brazed in a temperature range of 50 ° C. lower than the solidus temperature of the sliding member to 300 ° C., the nuclear / thermal power generation. Manufacturing method of plant valve device.
【請求項4】 鍛造又は圧延金属組織に共晶炭化物を有
し、該共晶炭化物の形状が非連続で30μm以下の塊状
又は粒状であるコバルト基合金、ニッケル基合金又は鉄
基合金を摺動部及び又は弁座部にろう付け接合する場
合、弁座部材とコバルト基合金、ニッケル基合金又は鉄
基合金の間にインサート材の箔、フラックス、ろう付け
用ペースト材等を介してろう付け接合されていることを
特徴とする原子力・火力発電プラント用装置の製造方
法。
4. Sliding a cobalt-based alloy, a nickel-based alloy or an iron-based alloy having a eutectic carbide in the forged or rolled metal structure, and the shape of the eutectic carbide is discontinuous and is lumpy or granular with a size of 30 μm or less. Part and / or valve seat part, by brazing with a valve seat member and cobalt-based alloy, nickel-based alloy or iron-based alloy with insert material foil, flux, brazing paste material, etc. A method for manufacturing a device for a nuclear power plant or a thermal power plant.
【請求項5】 鍛造又は圧延金属組織に共晶炭化物を有
し、該共晶炭化物の形状が非連続で30μm以下の塊状
又は粒状であるコバルト基合金、ニッケル基合金又は鉄
基合金を摺動部及び又は弁座部にろう付け接合する場
合、大気雰囲気中の電気炉、不活性ガス雰囲気中の電気
炉及び又は真空雰囲気中の電気炉を用いてろう付け接合
されることを特徴とする原子力・火力発電プラント用装
置の製造方法。
5. A slidable cobalt-based alloy, nickel-based alloy or iron-based alloy having a eutectic carbide in the forged or rolled metal structure, the shape of the eutectic carbide being discontinuous and in the form of lumps or particles of 30 μm or less. And / or valve seat portion is brazed, the nuclear reactor is characterized by being brazed using an electric furnace in an air atmosphere, an electric furnace in an inert gas atmosphere and / or an electric furnace in a vacuum atmosphere. -Method for manufacturing a thermal power plant device.
【請求項6】 鍛造又は圧延金属組織に共晶炭化物を有
し、該共晶炭化物の形状が非連続で30μm以下の塊状
又は粒状であるコバルト基合金、ニッケル基合金又は鉄
基合金を摺動部及び又は弁座部にろう付け接合する場
合、ろう付け接合時の押付け荷重を自重以上で10kg
/cm2以下としてろう付け接合されていることを特徴
とする原子力・火力発電プラント用装置の製造方法。
6. A slidable cobalt-based alloy, nickel-based alloy, or iron-based alloy having a eutectic carbide in the forged or rolled metal structure, the shape of the eutectic carbide being discontinuous and lumpy or granular with a size of 30 μm or less. When brazing to the valve and / or the valve seat, the pressing load during brazing is 10 kg or more when the weight is more than its own weight.
A method for manufacturing an apparatus for a nuclear power plant or a thermal power plant, which is brazed at a rate of not more than / cm 2 .
【請求項7】 鍛造又は圧延金属組織に共晶炭化物を有
し、該共晶炭化物の形状が非連続で30μm以下の塊状
又は粒状であるコバルト基合金、ニッケル基合金又は鉄
基合金を摺動部及び又は弁座部に摩擦圧接により接合さ
れていることを特徴とする原子力・火力発電プラント用
装置の製造方法。
7. A slidable cobalt-based alloy, nickel-based alloy or iron-based alloy having a eutectic carbide in the forged or rolled metal structure, the shape of the eutectic carbide being discontinuous and in the form of lumps or particles of 30 μm or less. Part and / or valve seat part is joined by friction welding to a nuclear / thermal power plant device manufacturing method.
JP2001220810A 2001-07-23 2001-07-23 Manufacturing method of nuclear/thermal power plant valve device Pending JP2003028315A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
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Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
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Publications (1)

Publication Number Publication Date
JP2003028315A true JP2003028315A (en) 2003-01-29

Family

ID=19054576

Family Applications (1)

Application Number Title Priority Date Filing Date
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Country Status (1)

Country Link
JP (1) JP2003028315A (en)

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