JPS6146793B2 - - Google Patents
Info
- Publication number
- JPS6146793B2 JPS6146793B2 JP54091017A JP9101779A JPS6146793B2 JP S6146793 B2 JPS6146793 B2 JP S6146793B2 JP 54091017 A JP54091017 A JP 54091017A JP 9101779 A JP9101779 A JP 9101779A JP S6146793 B2 JPS6146793 B2 JP S6146793B2
- Authority
- JP
- Japan
- Prior art keywords
- guide roller
- roller
- control rod
- wear
- supported
- 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
Links
- 229910045601 alloy Inorganic materials 0.000 claims description 16
- 239000000956 alloy Substances 0.000 claims description 16
- PXHVJJICTQNCMI-UHFFFAOYSA-N Nickel Chemical compound [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 claims description 12
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 claims description 8
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 claims description 8
- VYZAMTAEIAYCRO-UHFFFAOYSA-N Chromium Chemical compound [Cr] VYZAMTAEIAYCRO-UHFFFAOYSA-N 0.000 claims description 7
- 229910052804 chromium Inorganic materials 0.000 claims description 7
- 239000011651 chromium Substances 0.000 claims description 7
- 229910052759 nickel Inorganic materials 0.000 claims description 6
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 claims description 4
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 claims description 4
- 229910052782 aluminium Inorganic materials 0.000 claims description 4
- 229910052799 carbon Inorganic materials 0.000 claims description 4
- 229910052742 iron Inorganic materials 0.000 claims description 4
- 229910052757 nitrogen Inorganic materials 0.000 claims description 4
- 229910052710 silicon Inorganic materials 0.000 claims description 3
- 239000010703 silicon Substances 0.000 claims description 3
- WPBNNNQJVZRUHP-UHFFFAOYSA-L manganese(2+);methyl n-[[2-(methoxycarbonylcarbamothioylamino)phenyl]carbamothioyl]carbamate;n-[2-(sulfidocarbothioylamino)ethyl]carbamodithioate Chemical compound [Mn+2].[S-]C(=S)NCCNC([S-])=S.COC(=O)NC(=S)NC1=CC=CC=C1NC(=S)NC(=O)OC WPBNNNQJVZRUHP-UHFFFAOYSA-L 0.000 claims 1
- 239000010941 cobalt Substances 0.000 description 6
- 229910017052 cobalt Inorganic materials 0.000 description 6
- GUTLYIVDDKVIGB-UHFFFAOYSA-N cobalt atom Chemical compound [Co] GUTLYIVDDKVIGB-UHFFFAOYSA-N 0.000 description 6
- 230000007797 corrosion Effects 0.000 description 6
- 238000005260 corrosion Methods 0.000 description 6
- 230000005855 radiation Effects 0.000 description 6
- 238000001816 cooling Methods 0.000 description 5
- 230000000694 effects Effects 0.000 description 5
- 239000003921 oil Substances 0.000 description 5
- 229910001566 austenite Inorganic materials 0.000 description 4
- 230000000052 comparative effect Effects 0.000 description 4
- 239000000203 mixture Substances 0.000 description 3
- 239000000126 substance Substances 0.000 description 3
- GUTLYIVDDKVIGB-OUBTZVSYSA-N Cobalt-60 Chemical compound [60Co] GUTLYIVDDKVIGB-OUBTZVSYSA-N 0.000 description 2
- PWHULOQIROXLJO-UHFFFAOYSA-N Manganese Chemical compound [Mn] PWHULOQIROXLJO-UHFFFAOYSA-N 0.000 description 2
- XUIMIQQOPSSXEZ-UHFFFAOYSA-N Silicon Chemical compound [Si] XUIMIQQOPSSXEZ-UHFFFAOYSA-N 0.000 description 2
- 238000010273 cold forging Methods 0.000 description 2
- 238000005336 cracking Methods 0.000 description 2
- 238000005242 forging Methods 0.000 description 2
- 230000001771 impaired effect Effects 0.000 description 2
- 229910052748 manganese Inorganic materials 0.000 description 2
- 239000011572 manganese Substances 0.000 description 2
- 238000002844 melting Methods 0.000 description 2
- 230000008018 melting Effects 0.000 description 2
- 239000003758 nuclear fuel Substances 0.000 description 2
- 239000000047 product Substances 0.000 description 2
- 238000005482 strain hardening Methods 0.000 description 2
- 229910000859 α-Fe Inorganic materials 0.000 description 2
- ZOKXTWBITQBERF-UHFFFAOYSA-N Molybdenum Chemical compound [Mo] ZOKXTWBITQBERF-UHFFFAOYSA-N 0.000 description 1
- 229910000831 Steel Inorganic materials 0.000 description 1
- 229910001347 Stellite Inorganic materials 0.000 description 1
- RTAQQCXQSZGOHL-UHFFFAOYSA-N Titanium Chemical compound [Ti] RTAQQCXQSZGOHL-UHFFFAOYSA-N 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- AHICWQREWHDHHF-UHFFFAOYSA-N chromium;cobalt;iron;manganese;methane;molybdenum;nickel;silicon;tungsten Chemical compound C.[Si].[Cr].[Mn].[Fe].[Co].[Ni].[Mo].[W] AHICWQREWHDHHF-UHFFFAOYSA-N 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 230000006698 induction Effects 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 239000000314 lubricant Substances 0.000 description 1
- 150000001247 metal acetylides Chemical class 0.000 description 1
- 229910052750 molybdenum Inorganic materials 0.000 description 1
- 239000011733 molybdenum Substances 0.000 description 1
- 230000000737 periodic effect Effects 0.000 description 1
- 239000002244 precipitate Substances 0.000 description 1
- 238000001556 precipitation Methods 0.000 description 1
- 239000010959 steel Substances 0.000 description 1
- 239000010936 titanium Substances 0.000 description 1
- 229910052719 titanium Inorganic materials 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
- 238000003466 welding Methods 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
- Heat Treatment Of Articles (AREA)
Description
本発明原子力発電プラントの安全を確保するの
に好適な原子炉用制御棒に関する。
原子炉用制御棒は第１図に示したように軸方向
に沿つて十字状に組合せたブレード１の上部ハン
ドル２に、第２図に示した様に孔３を設け、その
孔３内にガイドローラ４をピン５で支持してい
る。またブレード１の下部には下部ハンドル６が
接続され、そのハンドル６の下方にリミツトロー
ラ７が設けられており、このリミツトローラ７は
第３図に示した様にピン８によつて支持されてい
る。なお、図中９は切込み部、１０はソケツト
部、１１は核燃料集合体をそれぞれ示し、第１図
ｂは制御棒全体の構成を一部省略して示す側面図
で同図ａはｂ図の上面図、同図ｃはｂ図の下面図
である。
しかして、原子炉の起動および停止、通常の出
力制御、さらには緊急時の停止および復帰等にお
いて、制御棒を駆動する際、ガイドローラ４およ
びリミツトローラ７が回転し止めピン５，８およ
び燃料集合体１１の側面と制御棒駆動機構の案内
筒との間で摩擦損耗を生じる。
ところで、一般にこの様な耐摩耗性を必要とす
る部品にはコバルトを約50％含有するいわゆるス
テライトと称する合金を使用するが、原子力プラ
ントでの使用においては摩擦損耗による生成物も
コバルトを含むため、原子炉内で使用する場合に
は中性子の照射によりコバルト60となつて放射線
源となり、原子力発電プラントの放射線量を増加
させる。そして、これらの蓄積された放射線源
は、原子力発電プラントの定期検査時における作
業従事者の被爆量を増加させ、ひいてはプラント
の稼動率を低下せしめることになる。
本発明は上述した点に鑑みてなされたもので、
制御棒のガイドローラ４およびリミツタローラ７
に耐摩耗ニツケル基合金を使用し、両ローラの止
めピン５，８に耐摩耗鉄基合金を使用して原子力
発電プラントの放射線量を低減させ得る制御棒を
提供することにある。
すなわち、本発明は重量比でクロム30〜40％、
アルミニウム２〜４％残部が実質的にニツケルよ
りなる合金で形成したガイドローラ４およびリミ
ツトローラ７を具備し、かつ重量比で炭素0.1％
以下、クロム16〜26％、マンガン5.5〜15％、ニ
ツケル5.5〜15％、けい素0.4〜５％、窒素0.05〜
0.6％および残部が実質的に鉄よりなる合金で形
成したガイドローラおよびリミツトローラの止め
ピン５，８を具備したことを特徴とする制御棒で
ある。
なお、前記ガイドローラ４およびリミツトロー
ラ７を構成する合金においてアルミニウムの一部
をチタンに置き換えること、および少量のモリブ
デンを添加することは本発明の効果を妨げない。
ここで本発明に係る原子炉用制御棒のガイドロ
ーラおよびリミツタローラを構成する合金の化学
成分の限定理由について説明する。クロムは耐摩
耗性を増加させるに必要な元素で、その量が30％
未満の場合には十分な耐摩性が得られずまた40％
を越えると鍛造加工が困難になることからこの範
囲とした。アルミニウムは耐摩耗性を向上させる
に必要な元素で、その量が２％未満では十分な耐
摩耗性が得られずまた４％を越えるとクロムと同
様に鍛造加工が困難となるのでこの範囲とする。
さらにガイドローラおよびリミツタローラ止め
ピンを構成する合金の化学成分の限定理由につい
て説明する。炭素はこの鋼のオーステナイトを安
定化するが、0.1％を越えると炭化物として折出
し応力腐食割れの原因となるので0.1％以下とす
る。クロムは耐食性と引張強さを向上させるに必
要な元素で16％未満ではその効果が十分でなく26
％を越えるとオーステナイト相の安定性が失わ
れ、熱間加工性が悪くなるのでこの範囲とする。
マンガンは耐摩耗性を向上させるに必要な元素で
5.5％未満ではその効果が十分でなく15％を越え
ると耐食性が損われるのでこの範囲とした。ニツ
ケルはオーステナイトを安定化させるに必要な元
素で5.5％未満ではフエライトを生成し耐食性が
失われる。15％を越えると炭素の溶解度を著しく
下げ、その結果多量の炭化物の折出を招いて応力
腐食割れを起すのでこの範囲とする。けい素は脱
酸剤として必要な元素で0.4％未満ではその効果
が十分でなく５％を越えるとフエライトを生成し
て耐食性を損うのでこの範囲とする。窒素はオー
ステナイトを安定化させる引張強さを向上させる
に必要な元素で0.05未満ではその効果が十分でな
く0.6％を越えると合金溶製および溶接の際にガ
ス化しやすく多孔質部分を生じるためこの範囲と
する。
次にこのガイドローラ４、リミツタローラ７お
よび止めピン５，８について実施例および比較例
をもつて説明する。表１に示した化学組成を持つ
合金を高周波誘導溶解により溶製した。この合金
に鍛造加工および熱処理を施した摩耗試験片とし
た。
The present invention relates to a nuclear reactor control rod suitable for ensuring the safety of a nuclear power plant. A control rod for a nuclear reactor has blades 1 arranged in a cross shape along the axial direction as shown in FIG. 1, and a hole 3 provided in the upper handle 2 as shown in FIG. A guide roller 4 is supported by a pin 5. A lower handle 6 is connected to the lower part of the blade 1, and a limit roller 7 is provided below the handle 6, and the limit roller 7 is supported by a pin 8 as shown in FIG. In addition, in the figure, 9 indicates a notch, 10 indicates a socket, and 11 indicates a nuclear fuel assembly. FIG. A top view, and figure c is a bottom view of figure b. Therefore, when driving the control rods during starting and stopping of a nuclear reactor, normal output control, and even stopping and returning in an emergency, the guide roller 4 and limit roller 7 are prevented from rotating and the stop pins 5, 8 and fuel assembly are driven. Frictional wear occurs between the side surface of the body 11 and the guide tube of the control rod drive mechanism. By the way, an alloy called stellite, which contains about 50% cobalt, is generally used for parts that require such wear resistance, but when used in nuclear power plants, the products of friction wear also contain cobalt. When used in a nuclear reactor, neutron irradiation turns cobalt-60 into a radiation source, increasing the radiation dose in a nuclear power plant. These accumulated radiation sources increase the amount of radiation that workers are exposed to during periodic inspections of nuclear power plants, which in turn reduces the operating rate of the plants. The present invention has been made in view of the above points, and
Control rod guide roller 4 and limiter roller 7
The object of the present invention is to provide a control rod that can reduce the radiation dose of a nuclear power plant by using a wear-resistant nickel-based alloy for the rollers and a wear-resistant iron-based alloy for the retaining pins 5 and 8 of both rollers. That is, the present invention contains 30 to 40% chromium by weight,
The guide roller 4 and the limit roller 7 are made of an alloy in which the balance is substantially nickel with 2 to 4% aluminum, and 0.1% carbon by weight.
Below, chromium 16-26%, manganese 5.5-15%, nickel 5.5-15%, silicon 0.4-5%, nitrogen 0.05-
This control rod is characterized in that it is equipped with guide roller and limit roller retaining pins 5 and 8 made of an alloy consisting essentially of 0.6% iron and the remainder iron. Note that replacing a portion of aluminum with titanium in the alloy constituting the guide roller 4 and limit roller 7 and adding a small amount of molybdenum do not impede the effects of the present invention. Here, the reason for limiting the chemical composition of the alloy constituting the guide roller and limiter roller of the nuclear reactor control rod according to the present invention will be explained. Chromium is an element necessary to increase wear resistance, and its amount is 30%
If it is less than 40%, sufficient wear resistance cannot be obtained.
This range was chosen because forging becomes difficult if it exceeds this range. Aluminum is an element necessary to improve wear resistance, and if the amount is less than 2%, sufficient wear resistance cannot be obtained, and if it exceeds 4%, it becomes difficult to forge like chromium, so it should not be within this range. do. Furthermore, the reason for limiting the chemical composition of the alloy constituting the guide roller and limiter roller fixing pin will be explained. Carbon stabilizes the austenite in this steel, but if it exceeds 0.1%, it will precipitate as carbides and cause stress corrosion cracking, so it should be kept at 0.1% or less. Chromium is an element necessary to improve corrosion resistance and tensile strength, and if it is less than 16%, the effect is not sufficient26
%, the stability of the austenite phase will be lost and hot workability will deteriorate, so it is set within this range.
Manganese is an element necessary to improve wear resistance.
If it is less than 5.5%, the effect will not be sufficient, and if it exceeds 15%, corrosion resistance will be impaired, so this range was set. Nickel is an element necessary to stabilize austenite, and if it is less than 5.5%, ferrite is formed and corrosion resistance is lost. If it exceeds 15%, the solubility of carbon will be significantly lowered, resulting in the precipitation of a large amount of carbide, which will cause stress corrosion cracking, so it is set within this range. Silicon is an element necessary as a deoxidizing agent, and if it is less than 0.4%, its effect will not be sufficient, and if it exceeds 5%, ferrite will be formed and corrosion resistance will be impaired, so it should be in this range. Nitrogen is an element necessary to stabilize austenite and improve its tensile strength.If it is less than 0.05%, its effect is insufficient, and if it exceeds 0.6%, it tends to gasify during alloy melting and welding, resulting in porous parts. range. Next, the guide roller 4, limiter roller 7, and stopper pins 5, 8 will be explained using examples and comparative examples. An alloy having the chemical composition shown in Table 1 was melted by high frequency induction melting. This alloy was forged and heat treated to produce wear test pieces.
【表】【table】
【表】
尚上記表において試験片処理条件と記号とは次
の関係にある。
ａ…1200℃×2h油冷、25％冷間鍛造、
600℃×10h
ｂ…1200℃×2h油冷、15％冷間鍛造、
600℃×2h
ｃ…熱間鍛造、1200℃油冷、700℃×1h
ｄ…鍛造のまま
ｅ…1050℃×2h油冷、35％冷間加工、
ｆ…1150℃×2h油冷、35％冷間加工、
495℃×3h
比較試験はアムスラー摩耗試験機を用い
回転数……210rpm
荷 重……30Kg
摩耗距離……1000ｍ
潤滑剤……水（200c.c.／ｈ）
の試験条件で行なつた。
その結果を総摩耗量として表２に示す。[Table] In the above table, the test piece processing conditions and symbols have the following relationship. a...1200℃×2h oil cooling, 25% cold forging, 600℃×10h b...1200℃×2h oil cooling, 15% cold forging, 600℃×2h c...hot forging, 1200℃ oil cooling, 700 ℃×1h d...As forged e...1050℃×2h oil cooling, 35% cold working, f...1150℃×2h oil cooling, 35% cold working, 495℃×3h Comparative test was conducted using Amsler wear tester. The test conditions were as follows: Number of revolutions used: 210 rpm Load: 30 kg Wear distance: 1000 m Lubricant: Water (200 c.c./h). The results are shown in Table 2 as the total wear amount.
【表】【table】
【表】
上記摩耗試験結果より明らかなように本発明に
係る制御棒においては、ガイドローラ４およびリ
ミツタローラ７を構成する合金とその止めピンを
構成する合金の耐摩耗性はそれぞれの比較例１−
１〜１−３および２−１〜２−４に示す合金より
優れており、比較例１−４および２−５のコバル
ト基耐摩耗合金と同等以上であつて、コバルトを
含有していないため、制御棒を駆動する際の摩擦
損耗による生成物もコバルトを含まず、原子炉内
で使用する場合もコバルトが放射化されて生じる
コバルト60の放射線量を増加させない。
以上述べた如く本発明に係る制御棒は、原子力
発電プラントにおける作業従事者の安全とプラン
ト稼動率の向上に頗る有用である。[Table] As is clear from the above wear test results, in the control rod according to the present invention, the wear resistance of the alloy forming the guide roller 4 and the limiter roller 7 and the alloy forming the retaining pin of each comparative example 1-
It is superior to the alloys shown in 1 to 1-3 and 2-1 to 2-4, is equivalent to or better than the cobalt-based wear-resistant alloys of Comparative Examples 1-4 and 2-5, and does not contain cobalt. The products produced by frictional wear and tear when driving the control rods do not contain cobalt, and when used in a nuclear reactor, they do not increase the radiation dose of cobalt-60, which is generated when cobalt is activated. As described above, the control rod according to the present invention is extremely useful for improving the safety of workers in nuclear power plants and the plant operating rate.
図面は本発明に係る制御棒を説明するためのも
ので、第１図は制御棒の全体を一部省略して示
し、同図ａは上面図、ｂは側面図、ｃは下面図、
第２図は第１図ｂにおけるＡ部を拡大して示す側
面図、第３図は第１図ｃにおけるＢ部を拡大して
示す側面図である。
１……ブレード、２……上部ハンドル、３……
孔、４……ガイドローラ、５……ピン、６……下
部ハンドル、７……リミツタローラ、８……ピ
ン、９……切込み部、１０……ソケツト部、１１
……核燃料集合体。
The drawings are for explaining the control rod according to the present invention, and FIG. 1 shows the entire control rod with some parts omitted, in which a is a top view, b is a side view, c is a bottom view,
FIG. 2 is an enlarged side view of section A in FIG. 1b, and FIG. 3 is an enlarged side view of section B in FIG. 1c. 1...Blade, 2...Upper handle, 3...
Hole, 4... Guide roller, 5... Pin, 6... Lower handle, 7... Limiter roller, 8... Pin, 9... Notch, 10... Socket part, 11
...Nuclear fuel assembly.
Claims (1)
の上方に連接する上部ハンドルに止めピンで軸支
されたガイドローラを設け、かつ前記ブレードの
下方に連接する下部ハンドル下端部に止めピンで
軸支されたリミツトローラを設けてなる原子炉用
制御棒において、前記ガイドローラおよびリミツ
トローラは、重量比で、クロム30〜40％、アルミ
ニウム２〜４％および残部が実質的にニツケルよ
りなる合金で構成され、かつ前記両止めピンは重
量比で、炭素0.1％以下、クロム16〜26％、マン
ガン5.5〜15％、ニツケル5.5〜15％、けい素0.4〜
5.0％、窒素0.05〜0.6％および残部が実質的に鉄
よりなる合金で構成されたことを特徴とする原子
炉用制御棒。1. A guide roller is provided which is supported by a stop pin on the upper handle connected above the blades which are combined in a cross shape along the axial direction, and a guide roller is supported by a stop pin at the lower end of the lower handle connected below the blade. In a control rod for a nuclear reactor provided with a supported limit roller, the guide roller and the limit roller are composed of an alloy consisting of 30 to 40% chromium, 2 to 4% aluminum, and the balance substantially nickel, by weight. , and the weight ratio of both retaining pins is 0.1% or less carbon, 16-26% chromium, 5.5-15% manganese, 5.5-15% nickel, and 0.4-0.4% silicon.
5.0% nitrogen, 0.05 to 0.6% nitrogen, and the balance substantially iron.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP9101779A JPS5614990A (en) | 1979-07-19 | 1979-07-19 | Nuclear reactor control rod |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP9101779A JPS5614990A (en) | 1979-07-19 | 1979-07-19 | Nuclear reactor control rod |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5614990A JPS5614990A (en) | 1981-02-13 |
| JPS6146793B2 true JPS6146793B2 (en) | 1986-10-16 |
Family
ID=14014791
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP9101779A Granted JPS5614990A (en) | 1979-07-19 | 1979-07-19 | Nuclear reactor control rod |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5614990A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0256493U (en) * | 1988-10-17 | 1990-04-24 |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5952228B2 (en) * | 1980-07-09 | 1984-12-18 | 株式会社日立製作所 | Sliding structure for nuclear reactor |
-
1979
- 1979-07-19 JP JP9101779A patent/JPS5614990A/en active Granted
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0256493U (en) * | 1988-10-17 | 1990-04-24 |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5614990A (en) | 1981-02-13 |
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