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JPH0723915B2 - Electric control rod drive mechanism for nuclear power plant - Google Patents
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JPH0723915B2 - Electric control rod drive mechanism for nuclear power plant - Google Patents

Electric control rod drive mechanism for nuclear power plant

Info

Publication number
JPH0723915B2
JPH0723915B2 JP60276867A JP27686785A JPH0723915B2 JP H0723915 B2 JPH0723915 B2 JP H0723915B2 JP 60276867 A JP60276867 A JP 60276867A JP 27686785 A JP27686785 A JP 27686785A JP H0723915 B2 JPH0723915 B2 JP H0723915B2
Authority
JP
Japan
Prior art keywords
control rod
pin
roller
drive mechanism
rod drive
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.)
Expired - Lifetime
Application number
JP60276867A
Other languages
Japanese (ja)
Other versions
JPS62137585A (en
Inventor
光雄 河合
薫 多田
憲行 中城
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 JP60276867A priority Critical patent/JPH0723915B2/en
Publication of JPS62137585A publication Critical patent/JPS62137585A/en
Publication of JPH0723915B2 publication Critical patent/JPH0723915B2/en
Anticipated expiration legal-status Critical
Expired - Lifetime 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

  • Transmission Devices (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Control Of Throttle Valves Provided In The Intake System Or In The Exhaust System (AREA)

Description

【発明の詳細な説明】 〔発明の技術分野〕 本発明は、制御棒の挿入・引抜きが円滑に出来かつ長期
間の使用が可能な原子力発電プラント用電動制御棒駆動
機構に関する。
Description: TECHNICAL FIELD OF THE INVENTION The present invention relates to an electric control rod drive mechanism for a nuclear power plant capable of smoothly inserting / pulling out a control rod and capable of long-term use.

〔発明の技術的背景および問題点〕[Technical background and problems of the invention]

従来、原子力発電プラントに使用されている制御棒駆動
機構は第1図に示すように、原子炉容器1の外側に突設
した筒体2の内側に制御棒3を支持する支持筒4挿着
し、炉水と制御棒駆動水とを遮断するシールリング5,6
を設けて、制御棒駆動水の供給により制御棒3を上下さ
せる構造であった。
Conventionally, a control rod drive mechanism used in a nuclear power plant is, as shown in FIG. 1, inserted into a support cylinder 4 for supporting a control rod 3 inside a cylindrical body 2 protruding from the outside of a reactor vessel 1. Seal ring 5, 6 that shuts off the reactor water and control rod drive water
And the control rod 3 is moved up and down by supplying control rod driving water.

しかし、最近燃料の有効利用および高精度の燃焼制御の
観点から、第2図に示すような原子炉容器11の外側に突
設した筒体12の内側に制御棒13を支持する中空ピストン
14を挿着し、ボールネジ軸15を介して電動機16により制
御棒13を上下さす構造の電動制御棒駆動機構が開発され
始めている。
However, recently, from the viewpoint of effective use of fuel and highly accurate combustion control, a hollow piston that supports a control rod 13 inside a cylindrical body 12 that projects from the outside of a reactor vessel 11 as shown in FIG.
An electric control rod drive mechanism having a structure in which 14 is inserted and the control rod 13 is moved up and down by a motor 16 via a ball screw shaft 15 has begun to be developed.

ところで、この電動制御棒駆動機構には、中空ピストン
14を長期間円滑に作動させるため、いいかえれば制御棒
13を長期間円滑に、かつ精度よく作動出来るように案内
用のピン/ローラ17〜25が装置されている。
By the way, this electric control rod drive mechanism has a hollow piston.
In other words, in order to operate 14 smoothly for a long time, in other words, control rod
Pins / rollers 17 to 25 for guiding are provided so that the 13 can be operated smoothly and accurately for a long period of time.

このピン/ローラは第3図に一例を示したように、ピン
31はピン固定部32に回り止めを有して固定され、ローラ
33はピン31を軸として回転する構造となっている。
This pin / roller has a pin, as shown in FIG.
31 is fixed to the pin fixing portion 32 with a detent,
33 has a structure that rotates about the pin 31.

この場合、ピン31の外周部はローラ33の内周部と摺動摩
擦を、またローラ外周部は第2図の中空ピストン14の外
周部や案内管17、その他ところがり摩擦を生じ摩耗す
る。
In this case, the outer peripheral portion of the pin 31 causes sliding friction with the inner peripheral portion of the roller 33, and the outer peripheral portion of the roller causes abrasion due to the outer peripheral portion of the hollow piston 14 shown in FIG.

このピン/ローラの場合のような耐摩耗性を必要とする
機械部品には、一般にコバルトを約50%含む通称ステラ
イトと呼ばれる合金が使用される。
Alloys commonly referred to as stellite containing approximately 50% cobalt are used for machine parts that require wear resistance, such as in the case of pins / rollers.

しかしながら、コバルト基合金で構成されたピン/ロー
ラを原子力発電プラント用電動制御棒駆動機構に使用す
ると、摩擦による摩耗生成物や腐食生成物などがコバル
トを含むため、これが電動制御棒駆動機構の冷却水によ
って原子炉中にもちきたされ、中性子の照射によりコバ
ルト60となり、原子力発電プラントの放射線線量率を上
昇させることになる。さらにこのコバルト60が蓄積する
と、原子力発電プラントの定期検査時における作業従事
者の放射線被爆量を増加させる虞れがあり、ひいてはプ
ラントの稼動率を低下させることにもなる。また一般の
金属材料を適用した場合には摩耗が著しく大きく、制御
棒の駆動が円滑に長期間使用出来ない。
However, when a pin / roller made of a cobalt-based alloy is used in an electric control rod drive mechanism for a nuclear power plant, wear products and corrosion products due to friction contain cobalt, which results in cooling of the electric control rod drive mechanism. It is brought into the reactor by water and becomes a cobalt-60 by neutron irradiation, which will increase the radiation dose rate of the nuclear power plant. Further, the accumulation of this cobalt 60 may increase the radiation exposure of workers during the periodic inspection of the nuclear power plant, which in turn lowers the operating rate of the plant. Further, when a general metal material is applied, the wear is extremely large, and the control rod cannot be smoothly driven for a long period of time.

〔発明の目的〕[Object of the Invention]

本発明はかかる点に鑑みてなされたもので、制御棒の挿
入、引抜きが円滑に出来、かつ長期間の使用が可能であ
るばかりでなく、コバルト60による放射線線量率の上昇
を抑制してプラントの稼働率向上を図った原子力発電プ
ラント用電動制御棒駆動機構を提供することを目的とし
たものである。
The present invention has been made in view of the above point, not only can the control rod be smoothly inserted and withdrawn, and can be used for a long period of time, as well as suppressing the increase of the radiation dose rate due to cobalt 60 in the plant. It is an object of the present invention to provide an electric control rod drive mechanism for a nuclear power plant with an improved operating rate.

〔発明の概要〕[Outline of Invention]

本発明は、原子炉容器の外側に突設した筒体の内側に制
御棒を支持する中空ピストンを装着し、ボールネジ軸を
介して電動機により制御棒を上下さす構造の原子力発電
プラント用の電動制御棒駆動機構であって、電動制御棒
駆動機構が、ピン取り付け部に回り止めを有して固定さ
れたピン及びピンを軸として回転するローラからなるピ
ン/ローラの組み合わせを装着しており、ローラがセラ
ミックよりなり、ピンは基体が金属でかつピンの少なく
ともローラの穴表面と摺動摩擦をする表面が窒化物セラ
ミック層で被覆されて成ることを特徴とする原子力発電
プラント用電動制御棒駆動機構である。本発明において
は、ピン/ローラの組み合わせにおいて、第4図、第5
図に示したようにローラ41セラミックであり、ピン42は
回り止めを有した基体が金属でかつピンの少なくともロ
ーラ穴表面と摺動摩擦する表面が窒化物セラミック43で
被覆されてなることを特徴とする。
The present invention is an electric control for a nuclear power plant having a structure in which a hollow piston supporting a control rod is mounted inside a cylindrical body protruding from the outside of a reactor vessel, and the control rod is moved up and down by an electric motor via a ball screw shaft. A rod drive mechanism, wherein the electric control rod drive mechanism is equipped with a pin / roller combination consisting of a pin fixed with a detent in the pin mounting portion and a roller that rotates about the pin. In the electric control rod drive mechanism for a nuclear power plant, the pin is made of ceramics, and the pin has a base body made of metal and at least the surface of the pin that makes sliding friction with the hole surface of the roller is covered with a nitride ceramic layer. is there. In the present invention, in the combination of pin / roller, FIG.
As shown in the figure, the roller 41 is a ceramic, and the pin 42 is characterized in that the base body having a detent is made of metal, and at least the surface of the pin that slides against the roller hole surface is covered with the nitride ceramic 43. To do.

ここで、本発明に係る電動制御棒駆動機構の限定理由に
ついて説明すると、ローラをセラミックとした理由はロ
ーラが従来より各種機器の耐摩耗部材として使用されて
いるコバルトを約50%含む通称ステライトと呼ばれる合
金である場合には前述したように摩耗による生成物や腐
食による生成物が冷却水により原子炉内部にもちきたさ
れ、中性子の照射でコバルト60となり原子力発電プラン
トの放射線線量率を上昇させることになり、また、一般
の金属材料ではステライトと同等の耐摩耗性が得られに
くい。しかし、ローラをセラミックとした場合にはコバ
ルトを含むことがなく、また金属材料に比べ耐摩耗性が
良いことによる。
Here, the reason for limiting the electric control rod drive mechanism according to the present invention will be explained. The reason why the roller is made of ceramic is that the roller is commonly known as stellite containing about 50% of cobalt which has been conventionally used as a wear resistant member of various devices. In the case of a so-called alloy, as described above, the products due to wear and the products due to corrosion are brought into the reactor by the cooling water, and the irradiation of neutrons turns them into cobalt 60 to increase the radiation dose rate of the nuclear power plant. In addition, it is difficult to obtain wear resistance equivalent to that of stellite with general metal materials. However, when the roller is made of ceramic, it does not contain cobalt and has better wear resistance than a metal material.

ローラと組合せて使用するピンを基体が金属でかつピン
の少なくともローラ穴表面と摺動摩擦をする表面がセラ
ミック、特に窒化層で被覆されて成る構造とした理由
は、ピンをコバルト基合金とした場合には摩耗生成物や
腐食生成物が冷却水により炉心にもちきたさせ中性子の
照射によりコバルト60が出来プラントの放射線線量率を
上昇させることとなるため、また一般の金属材料ではロ
ーラであるセラミックとの摩擦で摩耗量が多いこと、さ
らに、ピン全体をセラミックとした場合にはピンの直径
が細いため、機械的振動や地震などの衝撃力が働いた際
に破損しやすいためである。
The reason why the pin used in combination with the roller has a structure in which the substrate is made of metal and at least the surface of the pin that causes sliding friction with the roller hole surface is covered with a ceramic, especially a nitride layer, is because the pin is made of a cobalt-based alloy. In addition, wear products and corrosion products are brought to the core by cooling water and neutron irradiation produces cobalt-60, which increases the radiation dose rate of the plant. This is because there is a large amount of wear due to friction, and when the entire pin is made of ceramic, the diameter of the pin is thin, so that it is easily damaged when an impact force such as mechanical vibration or an earthquake acts.

〔発明の実施例〕Example of Invention

第1表に示すようにローラに相当する摩擦板を窒化硅素
とし、ローラ穴表面と接触するピン表面に相当する圧子
を市販のCr14%,W5%,Mo17%,残部Ni合金(通称ハステ
ロイC),および表面にプラズマPVDで炭化硅素を生成
させたもの、表面に窒化硅素粉末を塗布し真空中で焼成
したものをそれぞれ用意した。
As shown in Table 1, the friction plate corresponding to the roller is silicon nitride, and the indenter corresponding to the pin surface contacting the roller hole surface is commercially available Cr14%, W5%, Mo17%, balance Ni alloy (commonly known as Hastelloy C). , And a surface on which silicon carbide was generated by plasma PVD, and a surface on which silicon nitride powder was applied and baked in vacuum were prepared.

ついで、第5図に示すように摩擦と圧子接触させた状態
で摩擦板51を往復運動させ、所定の摺動距離を摺動させ
たのちに圧子52の試験前後の重量変化を測定した。な
お、摺動距離は100m,圧子にかかる荷重は50kg/cm2雰囲
気は室温水中とした。
Then, as shown in FIG. 5, the friction plate 51 was reciprocated in the state of friction and indenter contact, and after sliding a predetermined sliding distance, the weight change of the indenter 52 before and after the test was measured. The sliding distance was 100 m, and the load applied to the indenter was 50 kg / cm 2 atmosphere was room temperature water.

この結果、第1表に併記したように、比較例1は摩擦減
量が14.8mg/cm2であるのに対し、実施例1および実施例
2の摩擦減量は1mg/cm2以下と非常に少なく耐摩耗性が
優れており、制御棒駆動機構に装着して使用した場合に
コバルト60の発生がなく、長時間安定した制御棒の挿
入,引抜きが出来ることが判る。
As a result, as also shown in Table 1, Comparative Example 1 had a friction loss of 14.8 mg / cm 2 , whereas Example 1 and Example 2 had a very low friction loss of 1 mg / cm 2 or less. It has excellent wear resistance, and when mounted on a control rod drive mechanism, it does not generate cobalt 60, and it can be seen that the control rod can be inserted and pulled out stably for a long time.

なお、本発明に係るピン/ローラの組合せにおいて、該
ローラは窒化硅素のみでなく、炭化硅素や酸化ジルコニ
ウムあるいはアルミナ,窒化アルミニウムなどでも良
い。
In the pin / roller combination according to the present invention, the roller may be not only silicon nitride but also silicon carbide, zirconium oxide, alumina, aluminum nitride, or the like.

また該ピンの少なくともローラ穴の内面と接触して摺動
摩擦するピン表面のセラミックス層の生成方法としては
実施例のプラズマPVDや拡散接合のみでなく、一般の工
業的手法であるCVDや溶射あるいは基体金属を酸化させ
た酸化層でも良い。
Further, as a method of forming a ceramic layer on the surface of the pin that makes sliding contact and friction with at least the inner surface of the roller hole of the pin, not only plasma PVD and diffusion bonding in the examples but also general industrial methods such as CVD, thermal spraying or substrate It may be an oxide layer obtained by oxidizing a metal.

なお該ピンの基体金属としては望ましくは硬さの高い方
がよく、鉄基やニッケル基の析出硬化型合金がよい。
The base metal of the pin preferably has a high hardness, and an iron-based or nickel-based precipitation hardening alloy is preferable.

第1表における実施例2は以下の如くにして作成した。 Example 2 in Table 1 was prepared as follows.

チャンバー内に試料をセット後チャンバー内を真空排気
したのち、塩化チタンを水素をキャリヤーガスとして導
入するとともに窒素ガスを導入しチャンバー内の圧力を
約1torrにした。次いでプラズマ放電を行ない試料表面
に窒化チタンを生成した。(生成させた窒化チタンの厚
さは約2μmであった。) 次いでチャンバー内を真空排気したのち、塩化シリコン
を水素をキャリアガスとして導入するとともにメタンガ
スを導入後プラズマ放電を行ない試料表面に炭化硅素を
生成させた。
After setting the sample in the chamber and evacuating the chamber, titanium chloride was introduced as a carrier gas and nitrogen gas was introduced to adjust the pressure in the chamber to about 1 torr. Next, plasma discharge was performed to generate titanium nitride on the surface of the sample. (The thickness of the produced titanium nitride was about 2 μm.) Next, after the chamber was evacuated to a vacuum, silicon chloride was introduced as a carrier gas and methane gas was introduced, and then plasma discharge was performed to introduce silicon carbide onto the sample surface. Was generated.

(なお炭化硅素の厚さは約3〜4μmであった)。(Note that the thickness of the silicon carbide was about 3 to 4 μm).

この下地になるTiN層はSiC等のセラミック層の接合性を
良好とする。
The TiN layer as the base layer has good bondability with a ceramic layer such as SiC.

〔発明の他の実施例〕[Other Embodiments of the Invention]

第2表に示すようにローラに相当する摩擦板を窒化硅素
とし、ローラ穴表面と接触するピン表面に相当する圧子
を、C0.06%以下,Si1.0%以下,Mn4〜6%,Ni11.5〜13.5
%,Cr20.5〜23.5% Mo1.5〜3.0%,Nb+Ta0.1〜0.3,N0.
2〜0.4%,V0.1〜0.3%,残部鉄および付随的不純物より
成る通称XM−19と呼ばれる合金およびC0.05%以下,Si0.
1%以下,Mn0.1%以下,Ni7.5〜8.5%,Cr12.25〜13.27%,
Mo2.0〜2.5%,AC0.9〜1.35%,N0.01%以下残部鉄および
付随的不純物より成る通称PH13−8Moと呼ばれる合金と
これらの表面を窒化処理したものをそれぞれ用意した。
As shown in Table 2, the friction plate corresponding to the roller is made of silicon nitride, and the indenter corresponding to the pin surface in contact with the roller hole surface is C0.06% or less, Si1.0% or less, Mn4-6%, Ni11 .5 ~ 13.5
%, Cr20.5 to 23.5% Mo1.5 to 3.0%, Nb + Ta0.1 to 0.3, N0.
2 to 0.4%, V 0.1 to 0.3%, an alloy commonly called XM-19 consisting of balance iron and incidental impurities and C0.05% or less, Si0.
1% or less, Mn 0.1% or less, Ni7.5 to 8.5%, Cr12.25 to 13.27%,
An alloy called PH13-8Mo, which is composed of Mo2.0-2.5%, AC0.9-1.35%, N0.01% or less, and balance iron and incidental impurities, and those whose surfaces are nitrided were prepared.

さらに、市販のCr14%,W5%,Mo17%,残部Ni合金(通称
ハステロイC)も用意した。
Further, commercially available Cr14%, W5%, Mo17% and the balance Ni alloy (commonly known as Hastelloy C) were also prepared.

ついで、第5図に示すように摩擦板と圧子を接触させた
状態で摩擦板51を往復運動させ、所定の摺動距離を摺動
させたのちに圧子52の試験前後の重量変化を測定した。
なお摺動距離は100m,圧子にかかる荷重は50kg/cm2雰囲
気は室温水中とした。
Then, as shown in FIG. 5, the friction plate 51 was reciprocated in a state where the friction plate and the indenter were in contact with each other, and after sliding a predetermined sliding distance, the weight change of the indenter 52 before and after the test was measured. .
The sliding distance was 100 m, and the load applied to the indenter was 50 kg / cm 2 in room temperature water.

この結果、第1表に併記して示すように、比較例1〜3
の摩耗減量は10mg/cm2以上であるのに対し、実施例1お
よび2の摩耗減量は2mg/cm2以下と非常に少なく耐摩耗
性が優れており、制御棒駆動機構に装着して使用した場
合、コバルト60の発生がなく、長時間安定した制御棒の
挿入引抜きが出来ることが判る。
As a result, as shown together in Table 1, Comparative Examples 1 to 3
Wear loss is 10 mg / cm 2 or more, while the wear loss of Examples 1 and 2 is 2 mg / cm 2 or less, which is very small and has excellent wear resistance. When it is done, it can be seen that the control rod can be inserted and pulled out stably for a long time without the generation of cobalt 60.

なお窒化処理は以下の如く行なった。 The nitriding treatment was performed as follows.

試料を窒化処理装置にセットした後、アンモニアガスお
よびアンモニア分解ガスを流量約10/minで流しつつ、
試料を580℃±5℃に40時間加熱し表面に窒化層を生成
させた。(なおガスの分解率は約75%であった)。
After setting the sample in the nitriding device, while flowing ammonia gas and ammonia decomposition gas at a flow rate of about 10 / min,
The sample was heated to 580 ° C ± 5 ° C for 40 hours to form a nitride layer on the surface. (The gas decomposition rate was about 75%).

〔発明の効果〕〔The invention's effect〕

以上説明したように、本発明に係る原子力発電プラント
用電動制御棒駆動機構によれば、原子炉の起動停止や出
力の上昇下降に伴なう、ピン/ローラの摩擦抵抗や摩擦
損耗が小さく出来、長期間安定して制御棒の駆動を高精
度に行うことが出来、ひいてはプラントの稼動率の向上
を図れるなど顕著な効果を表わすものである。
As described above, according to the electric control rod drive mechanism for a nuclear power plant according to the present invention, it is possible to reduce the frictional resistance and frictional wear of the pin / roller that accompanies the start / stop of the reactor and the rise / fall of the output. In addition, the control rod can be driven with high accuracy in a stable manner for a long period of time, and the plant operating rate can be improved, which is a remarkable effect.

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

第1図は従来の水圧式制御棒駆動機構を示す縦断面図、 図中1は原子炉容器,2は筒体,3は制御棒,4は支持筒,5,6
はシールリング, 第2図は本発明に係る電動制御棒駆動機構を示す縦断面
図で,図中11は原子炉容器,12は筒体,13は制御棒,14は
中空ピストン,15はボールネジ軸,16は電動機,17〜25は
ピン/ローラ, 第3図はピン/ローラの取付部の一例を示す断面図で、
図中31はピン,32はピン固定部,33はローラ, 第4図は本発明に係るピン/ローラの取付部一例を示し
た断面図で、図中41はローラ,42はピン,43はセラミック
層,44はピン固定部, 第5図は摩耗試験方法を示した図で、図中51は摩擦板,5
2は圧子。
FIG. 1 is a longitudinal sectional view showing a conventional hydraulic control rod drive mechanism. In the figure, 1 is a reactor vessel, 2 is a cylinder, 3 is a control rod, 4 is a support cylinder, and 5, 6
Is a seal ring, and FIG. 2 is a longitudinal sectional view showing an electric control rod drive mechanism according to the present invention. In the figure, 11 is a reactor vessel, 12 is a cylinder, 13 is a control rod, 14 is a hollow piston, and 15 is a ball screw. Shaft, 16 is an electric motor, 17 to 25 are pins / rollers, and FIG. 3 is a sectional view showing an example of a pin / roller mounting portion.
In the drawing, 31 is a pin, 32 is a pin fixing part, 33 is a roller, and FIG. 4 is a sectional view showing an example of a pin / roller mounting part according to the present invention. In the figure, 41 is a roller, 42 is a pin, and 43 is a pin. Ceramic layer, 44 is a pin fixing part, Fig. 5 is a diagram showing a wear test method, in which 51 is a friction plate, 5
2 is an indenter.

フロントページの続き (56)参考文献 特開 昭58−33182(JP,A) 特開 昭58−172585(JP,A) 特開 昭55−161050(JP,A)Continuation of the front page (56) References JP-A-58-33182 (JP, A) JP-A-58-172585 (JP, A) JP-A-55-161050 (JP, A)

Claims (1)

【特許請求の範囲】[Claims] 【請求項1】原子炉容器の外側に突設した筒体の内側に
制御棒を支持する中空ピストンを装着し、ボールネジ軸
を介して電動機により制御棒を上下さす構造の原子力発
電プラント用の電動制御棒駆動機構であって、電動制御
棒駆動機構が、ピン取り付け部に回り止めを有して固定
されたピン及びピンを軸として回転するローラからなる
ピン/ローラの組み合わせを装着しており、ローラがセ
ラミックよりなり、ピンは基体が金属でかつピンの少な
くともローラの穴表面と摺動摩擦をする表面が窒化物セ
ラミック層で被覆されて成ることを特徴とする原子力発
電プラント用電動制御棒駆動機構。
1. An electric motor for a nuclear power plant having a structure in which a hollow piston supporting a control rod is mounted inside a cylindrical body projecting outside the reactor vessel, and the control rod is vertically moved by an electric motor via a ball screw shaft. A control rod drive mechanism, wherein the electric control rod drive mechanism is equipped with a pin / roller combination consisting of a pin fixed with a detent in the pin mounting portion and a roller rotating about the pin, An electric control rod drive mechanism for a nuclear power plant, characterized in that the roller is made of ceramic, and the pin has a base body made of metal and at least a surface of the pin that makes sliding friction with the hole surface of the roller is covered with a nitride ceramic layer. .
JP60276867A 1985-12-11 1985-12-11 Electric control rod drive mechanism for nuclear power plant Expired - Lifetime JPH0723915B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP60276867A JPH0723915B2 (en) 1985-12-11 1985-12-11 Electric control rod drive mechanism for nuclear power plant

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP60276867A JPH0723915B2 (en) 1985-12-11 1985-12-11 Electric control rod drive mechanism for nuclear power plant

Publications (2)

Publication Number Publication Date
JPS62137585A JPS62137585A (en) 1987-06-20
JPH0723915B2 true JPH0723915B2 (en) 1995-03-15

Family

ID=17575517

Family Applications (1)

Application Number Title Priority Date Filing Date
JP60276867A Expired - Lifetime JPH0723915B2 (en) 1985-12-11 1985-12-11 Electric control rod drive mechanism for nuclear power plant

Country Status (1)

Country Link
JP (1) JPH0723915B2 (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN110767328B (en) * 2019-10-31 2021-04-27 中海石油(中国)有限公司 Driving device and method for shutdown control rod in overturned state of floating nuclear power plant
CN110767327B (en) * 2019-10-31 2021-04-27 中海石油(中国)有限公司 Drive device and method for passive shutdown control rod in overturned state of floating nuclear power plant

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5833182A (en) * 1981-08-21 1983-02-26 株式会社日立製作所 Nuclear reactor control rod drive mechanism
JPS58172585A (en) * 1982-04-02 1983-10-11 株式会社日立製作所 Control rod drive mechanism

Also Published As

Publication number Publication date
JPS62137585A (en) 1987-06-20

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