JPH01180499A - Stainless steel tubular element having improved wear resistance - Google Patents
Stainless steel tubular element having improved wear resistanceInfo
- Publication number
- JPH01180499A JPH01180499A JP63002635A JP263588A JPH01180499A JP H01180499 A JPH01180499 A JP H01180499A JP 63002635 A JP63002635 A JP 63002635A JP 263588 A JP263588 A JP 263588A JP H01180499 A JPH01180499 A JP H01180499A
- Authority
- JP
- Japan
- Prior art keywords
- sleeve
- nitriding
- depth
- stainless steel
- chromium
- 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.)
- Granted
Links
- 229910001220 stainless steel Inorganic materials 0.000 title claims abstract description 16
- 239000010935 stainless steel Substances 0.000 title claims abstract description 16
- 238000005121 nitriding Methods 0.000 claims abstract description 16
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 claims abstract description 15
- 229910052757 nitrogen Inorganic materials 0.000 claims abstract description 9
- 239000001257 hydrogen Substances 0.000 claims abstract description 6
- 229910052739 hydrogen Inorganic materials 0.000 claims abstract description 6
- 238000000034 method Methods 0.000 claims description 14
- 230000008569 process Effects 0.000 claims description 7
- 239000011358 absorbing material Substances 0.000 claims description 6
- VNNRSPGTAMTISX-UHFFFAOYSA-N chromium nickel Chemical compound [Cr].[Ni] VNNRSPGTAMTISX-UHFFFAOYSA-N 0.000 claims description 6
- -1 nitrogen ions Chemical class 0.000 claims description 6
- 230000001590 oxidative effect Effects 0.000 claims description 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 4
- 229910000831 Steel Inorganic materials 0.000 claims 1
- 238000004519 manufacturing process Methods 0.000 claims 1
- 238000000992 sputter etching Methods 0.000 claims 1
- 239000010959 steel Substances 0.000 claims 1
- PXHVJJICTQNCMI-UHFFFAOYSA-N nickel Substances [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 abstract description 7
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 abstract description 5
- 229910052759 nickel Inorganic materials 0.000 abstract description 4
- 239000000725 suspension Substances 0.000 abstract description 2
- 239000007789 gas Substances 0.000 abstract 1
- 238000010438 heat treatment Methods 0.000 abstract 1
- 238000000576 coating method Methods 0.000 description 3
- 238000007747 plating Methods 0.000 description 3
- VYZAMTAEIAYCRO-UHFFFAOYSA-N Chromium Chemical compound [Cr] VYZAMTAEIAYCRO-UHFFFAOYSA-N 0.000 description 2
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical group [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 2
- 229910000589 SAE 304 stainless steel Inorganic materials 0.000 description 2
- 239000011651 chromium Substances 0.000 description 2
- 239000011248 coating agent Substances 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 238000009792 diffusion process Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000009713 electroplating Methods 0.000 description 2
- 239000000446 fuel Substances 0.000 description 2
- 150000002500 ions Chemical class 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 229910052751 metal Inorganic materials 0.000 description 2
- 239000002184 metal Substances 0.000 description 2
- 239000001301 oxygen Substances 0.000 description 2
- 229910052760 oxygen Inorganic materials 0.000 description 2
- 238000002161 passivation Methods 0.000 description 2
- 230000009257 reactivity Effects 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- AHOUBRCZNHFOSL-YOEHRIQHSA-N (+)-Casbol Chemical compound C1=CC(F)=CC=C1[C@H]1[C@H](COC=2C=C3OCOC3=CC=2)CNCC1 AHOUBRCZNHFOSL-YOEHRIQHSA-N 0.000 description 1
- 241000239290 Araneae Species 0.000 description 1
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 1
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 1
- 241000237858 Gastropoda Species 0.000 description 1
- 229910018487 Ni—Cr Inorganic materials 0.000 description 1
- 230000002745 absorbent Effects 0.000 description 1
- 239000002250 absorbent Substances 0.000 description 1
- 230000009471 action Effects 0.000 description 1
- 229910045601 alloy Inorganic materials 0.000 description 1
- 239000000956 alloy Substances 0.000 description 1
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 1
- 229910052796 boron Inorganic materials 0.000 description 1
- 229910052799 carbon Inorganic materials 0.000 description 1
- 229910052804 chromium Inorganic materials 0.000 description 1
- UFGZSIPAQKLCGR-UHFFFAOYSA-N chromium carbide Chemical compound [Cr]#C[Cr]C#[Cr] UFGZSIPAQKLCGR-UHFFFAOYSA-N 0.000 description 1
- 239000000498 cooling water Substances 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 238000003795 desorption Methods 0.000 description 1
- 230000001627 detrimental effect Effects 0.000 description 1
- 238000010494 dissociation reaction Methods 0.000 description 1
- 230000005593 dissociations Effects 0.000 description 1
- 239000008246 gaseous mixture Substances 0.000 description 1
- 238000002513 implantation Methods 0.000 description 1
- 239000012535 impurity Substances 0.000 description 1
- 238000010849 ion bombardment Methods 0.000 description 1
- 229910052742 iron Inorganic materials 0.000 description 1
- 239000011159 matrix material Substances 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 239000008188 pellet Substances 0.000 description 1
- 230000004044 response Effects 0.000 description 1
- 230000009897 systematic effect Effects 0.000 description 1
- 238000005382 thermal cycling Methods 0.000 description 1
- 229910003470 tongbaite Inorganic materials 0.000 description 1
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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Solid-Phase Diffusion Into Metallic Material Surfaces (AREA)
Abstract
Description
【発明の詳細な説明】
〔産業上の利用分野〕
本発明は、水で冷却および減速される原子炉の高圧・高
温水中で利用されるように設計された、クロム−ニッケ
ル・ステンレス鋼製管状要素に関する。DETAILED DESCRIPTION OF THE INVENTION [Industrial Application] The present invention relates to a chromium-nickel stainless steel tubular product designed for use in the high-pressure, high-temperature water of water-cooled and moderated nuclear reactors. Regarding elements.
この種の原子炉において、冷却水はしばしば硼素生成物
を含有し、それが管状要素に接触するようになっており
、管状要素のいくつかはしばしば、ガイド内をそれに沿
って摺動移動され、それをこするようになっている。In this type of reactor, the cooling water often contains boron products, which come into contact with the tubular elements, some of which are often moved along by sliding in guides. It is supposed to be rubbed.
これは特に、反応度制御棒クラスタ（集合体）のステン
レス鋼製スリーブにおいて起こる。原子炉の反応度を制
御するため、制御棒は燃料装置に設けられるガイドチュ
ーブに沿って、そして原子炉の内項部に設けられるガイ
ドに沿って移動される。特に原子炉が“負荷追従”（ｌ
ｏａｄｆ’ｏｌ １ｏｖｅｒ）様式で用いられる時の幾
つかの制御棒の移動の周期および振幅は、各炉心再負荷
（ｃｏ、ｒｅｒｅｌｏａｄｉｎｇ ）において幾つかの
クラスタを系統的に交換することがしばしば必要となる
程である。This occurs particularly in stainless steel sleeves of reactivity control rod clusters. To control the reactivity of a nuclear reactor, control rods are moved along guide tubes provided in the fuel system and along guides provided in the inner core of the reactor. In particular, nuclear reactors are “load following” (l
The period and amplitude of movement of several control rods when used in an oadf'ol over mode often requires systematic replacement of several clusters at each core reloading (co, rereloading). That's about it.
摩擦を受ける管状要素の外面に、その摩耗を減少させる
ためにコーティングを付着させることは既に提案されて
いる。例えば、硬質クロムの電解メツキおよびニッケル
の化学メツキがこれまでに行なわれてきた。It has already been proposed to apply a coating to the external surface of a tubular element which is subject to friction in order to reduce its wear. For example, electrolytic plating of hard chromium and chemical plating of nickel have been performed in the past.
しかし、電解クロムメツキはもろいし、一方、化学的に
付着されたニッケルは原子炉の主回路を汚染することが
ある。また、ニッケルークロム結合合金が付加された炭
化クロムを含有するコーティングは、放射線被爆下にお
ける挙動が劣る。However, electrolytic chrome plating is brittle, while chemically deposited nickel can contaminate the reactor's main circuits. Also, coatings containing chromium carbide with added nickel-chromium bond alloys behave poorly under radiation exposure.
従って、本発明の目的は、ステンレス鋼製管状要素の摩
耗に対する耐久性を改善することにある。本発明の他の
目的は、熱サイクルに対する上記管状要素の耐久性を増
大すると共に、水冷原子炉中での放射線被爆下での特性
を維持することにある。It is therefore an object of the invention to improve the wear resistance of stainless steel tubular elements. Another object of the invention is to increase the durability of the tubular element to thermal cycling while maintaining its properties under radiation exposure in a water-cooled nuclear reactor.
本発明によれば、その外面が１５〜４０ミクロンの深さ
まで窒化されたクロム−ニッケル・ステンレス鋼からな
る管状要素、典型的には原子炉用制御棒シースが提供さ
れる。In accordance with the present invention, there is provided a tubular element, typically a control rod sheath for a nuclear reactor, made of chromium-nickel stainless steel whose outer surface is nitrided to a depth of 15 to 40 microns.
窒化はイオン化状態で実施されることが有利である。管
状要素は窒素および水素を含有する稀薄（ｒａｒｉｆ’
１ｅｄ）雰囲気内での放電により作り出されるプラズマ
を受けて、イオンの深部拡散をもたらすに十分な高温に
おいて活性窒素イオンが注入される。Advantageously, the nitridation is carried out in the ionized state. The tubular elements contain nitrogen and hydrogen containing rarif'
1ed) Activated nitrogen ions are implanted at a high enough temperature to cause deep diffusion of the ions in response to a plasma created by a discharge in an atmosphere.
酸化媒体中での耐食性に対して有害な管状要素のマトリ
ックスの脱り６ムによる材料の増感状態を避けるために
、処理層が４０μｍを越えないように十分に低い処理時
間および温度を採用することが望ましい。実際には、約
５００℃の温度で数時間処理することが可能である。In order to avoid a sensitized state of the material due to desorption of the matrix of the tubular elements, which is detrimental to the corrosion resistance in oxidizing media, treatment times and temperatures low enough are adopted so that the treatment layer does not exceed 40 μm. This is desirable. In practice, it is possible to process for several hours at temperatures of approximately 500°C.
耐摩耗性をさらに増大するために、管状要素はイオン的
に表面不動態化することができる。To further increase wear resistance, the tubular elements can be ionically surface passivated.
不動態化は、窒化された管状要素を、不動態化厚さが窒
化深さを越えず、かつ１時間より長く選択された時間、
５００℃より低温において酸化プラズマ中に維持するこ
とにより行なわれる。Passivating the nitrided tubular element for a selected period of time, such that the passivation thickness does not exceed the nitridation depth and is greater than 1 hour.
This is done by maintaining it in an oxidizing plasma at a temperature below 500°C.
以下、添附図面を参照しながら、本発明の特定の実施例
について説明するが、本発明が下記実施例に限定される
ものでないことはもとよりである。Hereinafter, specific embodiments of the present invention will be described with reference to the accompanying drawings, but it goes without saying that the present invention is not limited to the following embodiments.
第１図は加圧水型原子炉の制御クラスタの一つのロッド
１０を示している。ロッド１０および他のロッド類は複
数のロッドを同時に垂直移動させるためのスパイダー１
２の腕部に固定されている。FIG. 1 shows one rod 10 of a control cluster of a pressurized water reactor. Rod 10 and other rods are spiders 1 for vertically moving multiple rods simultaneously.
It is fixed to the arm of 2.
ロッド類はガイドチューブ１４内を摺動し、該ガイドチ
ューブ１４は燃料装置に属すると共に端部ノズル１６に
連結されている。The rods slide within a guide tube 14 that belongs to the fuel system and is connected to an end nozzle 16.
各ロッドは、クロム−ニッケル・ステンレス鋼、しばし
ばＡＩＳＩ３０４鋼からなるシースまたはスリーブ１８
を備えており、上記ＡＩＳ■３０４鋼の主成分は次の通
りである。Ｎｉ：８．５０〜１１重量％、Ｃｒ：１７〜
１９重量％、炭素：最大８重量％、Ｍｎ：最大２重量％
。残りは避けられない不純物を除いて鉄である。中性子
吸収材からなるペレット２０（またはスラグ）がスリー
ブ内に堆積されている。スリーブ１８は、同様にステン
レス鋼からなる上部プラグ２２および下部プラグ２４に
より密封閉鎖されている。 −例として、スリーブ１８
は９〜２５ｍ＋ｓの外径、および約０ 、４ ｍｍ 〜
１ 、 ５ ｍｍの肉厚を有することができる。スリー
ブは径が大きくなればなる程厚肉にすればよい。Each rod has a sheath or sleeve 18 made of chrome-nickel stainless steel, often AISI 304 steel.
The main components of the AIS ■304 steel are as follows. Ni: 8.50~11% by weight, Cr: 17~
19% by weight, carbon: max. 8% by weight, Mn: max. 2% by weight
. The rest is iron, with the exception of unavoidable impurities. Pellets 20 (or slugs) of neutron absorbing material are deposited within the sleeve. The sleeve 18 is hermetically closed by an upper plug 22 and a lower plug 24, also made of stainless steel. - As an example, sleeve 18
has an outer diameter of 9 to 25 m+s, and approximately 0,4 mm to
It can have a wall thickness of 1.5 mm. The larger the diameter of the sleeve, the thicker the sleeve should be.
一般に同様にステンレス鋼からなるガイドチューブ１４
上を摩擦摺動する時のシース１８の摩耗および引裂きを
低減するため、１５〜４０μｍ１典型的には２０〜４０
μｍの深さの表面窒化処理が行なわれる。Guide tube 14, generally also made of stainless steel
15-40 μm 1 typically 20-40 μm to reduce wear and tear on the sheath 18 during frictional sliding thereon.
A surface nitriding process is performed to a depth of μm.
窒化は第２図に概略的に示される装置において行なわれ
る。第２図の装置は密閉された包囲体２６を備えており
、これには、内部の圧力を通常は３０〜２００パスカル
の値まで減少させるための真空ポンプ２８と、窒素およ
び水素の混合体を導入するための流入パイプとが設けら
れている。包囲体２６は処理される複数のスリーブから
なる１装填量を受容する懸架装置を包含している。操作
順序は以下のように行なわれる。The nitriding is carried out in an apparatus shown schematically in FIG. The apparatus of FIG. 2 comprises a sealed enclosure 26, which includes a vacuum pump 28 to reduce the internal pressure to a value typically between 30 and 200 Pascals, and a mixture of nitrogen and hydrogen. An inlet pipe is provided for the introduction. Enclosure 26 includes a suspension system for receiving a charge of sleeves to be processed. The sequence of operations is as follows.
処理されるスリーブは洗浄されて、その下部プラグ２４
が嵌合される。ステンレス鋼のスラグから構成され得る
熱緩衝体が各スリーブ１８内に配置されてから、仮の上
部プラグ３２が各スリーブに固定される。該プラグはコ
ーティング中のスリーブを保持するために用いられる。The sleeve to be processed is cleaned and its lower plug 24
are fitted. A thermal buffer, which may be comprised of a stainless steel slug, is placed within each sleeve 18 before a temporary top plug 32 is secured to each sleeve. The plug is used to hold the sleeve during coating.
スリーブ１８は包囲体２６内に置かれ、その上部プラグ
３２に近接する部分は、この領域におけるステンレス鋼
の窒化を避けるためにマスキングすることが有利である
。The sleeve 18 is placed within the enclosure 26 and its portion adjacent to the upper plug 32 is advantageously masked to avoid nitriding of the stainless steel in this area.
各部分は、包囲体２６内で、約３０Ｐａの圧力下におい
てイオン的にエツチングされる。次いで、包囲体は掃気
されて、低圧（総圧力は２００Ｐ ａを越えず、また窒
素分圧はたとえば４０〜６０Ｐａ）の窒素および水素雰
囲気が発生される。３００ｖ〜１００ＯＶの電圧が、発
電機３４により、金属製包囲体２６と処理されるスリー
ブ１８との間に印加される。放電によるガス状混合体の
解離により形成へれる活性窒素イオンが、スリーブ１８
の表面にイオン衝撃により打ち込まれる。Each portion is ionically etched within the enclosure 26 under a pressure of approximately 30 Pa. The enclosure is then purged to generate a low pressure nitrogen and hydrogen atmosphere (total pressure not exceeding 200 Pa and nitrogen partial pressure, for example 40-60 Pa). A voltage between 300v and 100OV is applied by a generator 34 between the metal enclosure 26 and the sleeve 18 being treated. Activated nitrogen ions formed by the dissociation of the gaseous mixture by the electrical discharge enter the sleeve 18.
is implanted into the surface by ion bombardment.
スリーブをその全長にわたって、周囲゛温度より高いが
５１０℃（典型的には、約５００℃）より低い温度に維
持して、窒素イオンの拡散をもたらすための手段（図示
しない）が設けられ、この装置は通常のものとすること
ができる。この操作は注入の深さが所望値になるまで続
けられる。しかし実際には、処理時間は６時間を越えな
い。 ″
包囲体２６は再度掃気されて、窒化中とほぼ同じ圧力下
において、酸素を含有する酸化雰囲気を充填される。こ
の場合には活性酸素イオンを含有するプラズマが発生さ
れて、窒化層が限定的に酸化される。この工程は４００
〜４８０℃の温度で、適切な不動態化が達成されるまで
実施される。一般に、持続時間は１時間よりは長く、か
つ窒素イオンにより達成されたものより大きい深さまで
金属を不動態化する時間より短くされる。Means (not shown) are provided for maintaining the sleeve over its length at a temperature above ambient temperature but below 510°C (typically about 500°C) to effect diffusion of nitrogen ions; The device can be conventional. This operation continues until the desired depth of implantation is achieved. However, in practice, the processing time does not exceed 6 hours. '' The enclosure 26 is again scavenged and filled with an oxidizing atmosphere containing oxygen under approximately the same pressure as during nitriding. In this case, a plasma containing active oxygen ions is generated to confine the nitrided layer. This process is 400
It is carried out at a temperature of ˜480° C. until adequate passivation is achieved. Generally, the duration will be greater than 1 hour and less than the time to passivate the metal to a greater depth than that achieved with nitrogen ions.
次いで、スリーブ１８は包囲体２６から取出される。仮
の上部プラグ３２が取りはずされて、スリーブ１８は吸
収性材料を装填されて、最終上部プラグが載置される。Sleeve 18 is then removed from enclosure 26. The temporary top plug 32 is removed, the sleeve 18 is loaded with absorbent material, and the final top plug is placed.
変形例としては、スリーブはイオン窒化処理前に中性子
吸収材が装填されて閉鎖される゛。Alternatively, the sleeve is loaded with neutron absorbing material and closed before the ion nitriding process.
本発明は制御棒（ロッド）以外の原子炉内で用いられる
管状要素に適用できる。The present invention can be applied to tubular elements used in nuclear reactors other than control rods.
本発明は、特に、他の機能を有すると共に、その表面が
摩擦または振動摩耗に耐えなければならないロッドクラ
スタに利用できる。The invention is particularly applicable to rod clusters which have other functions and whose surfaces must withstand frictional or vibrational wear.
また、内部を摺動する部材の摩擦を受けるような管類の
内面に同様の処理を行なうことも可能である。It is also possible to perform a similar treatment on the inner surface of tubing that is subject to friction from members sliding inside.
以上のように、本発明のクロム−ニッケル・ステンレス
鋼製管状要素は、１５〜４０μｍの深さにわたって表面
窒化されたものであるため、従来のような電解メツキあ
るいは化学メツキのような問題もなく、高圧及び高温水
中下でも優れた耐摩擦性を示し、また、水冷原子炉中で
の放射線被爆下においてもこのような優れた特性を維持
することができる。従って、中性子吸収材を装填するた
めの制御棒のスリーブ（シース）として極めて有用であ
り、制御棒の出し入れの際のガイドチューブとの摩擦に
おいても優れた耐摩耗性を発揮する原子炉用制御棒が提
供される。また、本発明の方法によれば比較的短時間に
上記のような優れた特性を有する管状要素あるいは制御
棒が製造できる。As described above, since the chromium-nickel stainless steel tubular element of the present invention is surface nitrided to a depth of 15 to 40 μm, there are no problems associated with conventional electrolytic plating or chemical plating. It exhibits excellent friction resistance even under high pressure and high temperature water, and can maintain such excellent properties even under radiation exposure in a water-cooled nuclear reactor. Therefore, it is extremely useful as a control rod sleeve (sheath) for loading neutron absorbing material, and is a control rod for nuclear reactors that exhibits excellent wear resistance against friction with the guide tube when the control rod is inserted and removed. is provided. Further, according to the method of the present invention, tubular elements or control rods having the above-mentioned excellent properties can be manufactured in a relatively short time.
第１図は、本発明により処理されるシースを備える制御
クラスタの１本のロッドを示す部分断面概略図、第２図
は本発明の実施例によるシース処理装置の概略図である
。
１８・・・スリーブ（もしくはシース）、２０・・・中
性子吸収材、２２・・・上部プラグ、２４・・・下部プ
ラグ、２６・・・包囲体。FIG. 1 is a partial cross-sectional schematic diagram showing one rod of a control cluster with a sheath treated according to the invention, and FIG. 2 is a schematic diagram of a sheath treatment device according to an embodiment of the invention. 18... Sleeve (or sheath), 20... Neutron absorbing material, 22... Upper plug, 24... Lower plug, 26... Enclosure.
Claims (1)
、水減速および水冷の原子炉用のクロム−ニッケル・ス
テンレス鋼製管状要素。 （２）クロム−ニッケル・ステンレス鋼からなる外部ス
リーブと、該スリーブ内の中性子吸収材とから成り、前
記スリーブが１５〜４０μｍの深さまで表面窒化処理さ
れている加圧水型原子炉用原子炉制御棒。 （３）ステンレス鋼がＡＩＳＩ３４０鋼であることを特
徴とする請求項２記載の制御棒。（４）前記スリーブが
最大で窒化深さに等しい深さにわたって表面不動態化さ
れている請求項３記載の制御棒。 （５）クロム−ニッケル・ステンレス鋼製スリーブを用
意し、該スリーブを減圧下で窒素−水素雰囲気中に維持
すると共に、前記雰囲気中に放電を生ぜしめて窒素イオ
ンを発生させることにより、前期スリーブの半径方向外
面を窒化することからなる、水冷・減速される原子炉用
シースの製造方法。 （６）前記窒化を、５１０℃を越えない温度において６
時間までの持続時間で実施する請求項５記載の方法。 （７）包囲体内での窒化処理前に前記包囲体内でイオン
・エッチングの予備処理を実施する工程を含む請求項５
記載の方法。 （８）窒化処理前に前記スリーブに熱緩衝体を充填して
プラグにより閉鎖するようにした請求項５記載の方法。 （９）窒化処理前に前記スリーブに中性子吸収材を充填
して閉鎖するようにした請求項５記載の方法。 （１０）窒化処理の直後に酸化雰囲気中でプラズマを発
生させることにより、最大で窒化深さに等しい深さにわ
たって表面的に不動態化する工程をさらに含む請求項５
記載の方法。Claims: (1) A chromium-nickel stainless steel tubular element for water-moderated and water-cooled nuclear reactors, surface nitrided to a depth of 15 to 40 μm. (2) A reactor control rod for a pressurized water reactor consisting of an external sleeve made of chromium-nickel stainless steel and a neutron absorbing material within the sleeve, the sleeve being surface nitrided to a depth of 15 to 40 μm. . (3) The control rod according to claim 2, wherein the stainless steel is AISI340 steel. 4. The control rod of claim 3, wherein said sleeve is surface passivated to a depth up to a depth equal to the nitridation depth. (5) A chromium-nickel stainless steel sleeve is prepared, the sleeve is maintained in a nitrogen-hydrogen atmosphere under reduced pressure, and a discharge is generated in the atmosphere to generate nitrogen ions. A method of manufacturing a water-cooled and moderated nuclear reactor sheath comprising nitriding the radially outer surface. (6) The nitriding is carried out at a temperature not exceeding 510°C.
6. The method of claim 5, wherein the method is carried out for a duration of up to hours. (7) Claim 5, further comprising the step of performing a pretreatment of ion etching within the enclosure before the nitriding treatment within the enclosure.
Method described. (8) The method according to claim 5, wherein the sleeve is filled with a thermal buffer and closed with a plug before the nitriding process. (9) The method according to claim 5, wherein the sleeve is filled with a neutron absorbing material and closed before the nitriding treatment. (10) Immediately after the nitriding process, the process further comprises the step of superficially passivating a depth equal to the nitriding depth by generating plasma in an oxidizing atmosphere.
Method described.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63002635A JP2657810B2 (en) | 1988-01-11 | 1988-01-11 | Stainless steel tubular elements with improved wear resistance |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63002635A JP2657810B2 (en) | 1988-01-11 | 1988-01-11 | Stainless steel tubular elements with improved wear resistance |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH01180499A true JPH01180499A (en) | 1989-07-18 |
| JP2657810B2 JP2657810B2 (en) | 1997-09-30 |
Family
ID=11534845
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP63002635A Expired - Lifetime JP2657810B2 (en) | 1988-01-11 | 1988-01-11 | Stainless steel tubular elements with improved wear resistance |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2657810B2 (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2016504487A (en) * | 2012-11-07 | 2016-02-12 | アレバ・エヌペ | Method for thermochemical treatment of parts while partly covering and corresponding mask |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6035989A (en) * | 1983-08-09 | 1985-02-23 | Ricoh Co Ltd | Control system of dc motor |
| JPS60262955A (en) * | 1984-06-06 | 1985-12-26 | レイデイオロジカル アンド ケミカル テクノロジ− インコ−ポレ−テツド | Inactivation of stainless steel member surface |
| JPS61295377A (en) * | 1985-06-20 | 1986-12-26 | バルツエルス アクチエンゲゼルシヤフト | Formation of membrane |
| JPS6235289A (en) * | 1985-08-08 | 1987-02-16 | ウエスチングハウス エレクトリック コ−ポレ−ション | Supporter for control rod of nuclear reactor |
| US4704168A (en) * | 1984-10-16 | 1987-11-03 | The United States Of America As Represented By The Administrator Of The National Aeronautics And Space Administration | Ion-beam nitriding of steels |
-
1988
- 1988-01-11 JP JP63002635A patent/JP2657810B2/en not_active Expired - Lifetime
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6035989A (en) * | 1983-08-09 | 1985-02-23 | Ricoh Co Ltd | Control system of dc motor |
| JPS60262955A (en) * | 1984-06-06 | 1985-12-26 | レイデイオロジカル アンド ケミカル テクノロジ− インコ−ポレ−テツド | Inactivation of stainless steel member surface |
| US4704168A (en) * | 1984-10-16 | 1987-11-03 | The United States Of America As Represented By The Administrator Of The National Aeronautics And Space Administration | Ion-beam nitriding of steels |
| JPS61295377A (en) * | 1985-06-20 | 1986-12-26 | バルツエルス アクチエンゲゼルシヤフト | Formation of membrane |
| JPS6235289A (en) * | 1985-08-08 | 1987-02-16 | ウエスチングハウス エレクトリック コ−ポレ−ション | Supporter for control rod of nuclear reactor |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2016504487A (en) * | 2012-11-07 | 2016-02-12 | アレバ・エヌペ | Method for thermochemical treatment of parts while partly covering and corresponding mask |
| US10625300B2 (en) | 2012-11-07 | 2020-04-21 | Areva Np | Method for thermochemically treating a part while masking a portion and corresponding mask |
Also Published As
| Publication number | Publication date |
|---|---|
| JP2657810B2 (en) | 1997-09-30 |
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