JPS62181834A - Manufacturing method for pipe used in nuclear power plant - Google Patents
Manufacturing method for pipe used in nuclear power plantInfo
- Publication number
- JPS62181834A JPS62181834A JP2012986A JP2012986A JPS62181834A JP S62181834 A JPS62181834 A JP S62181834A JP 2012986 A JP2012986 A JP 2012986A JP 2012986 A JP2012986 A JP 2012986A JP S62181834 A JPS62181834 A JP S62181834A
- Authority
- JP
- Japan
- Prior art keywords
- polishing
- sus316
- piping
- accumulation
- nuclear power
- 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
- 238000004519 manufacturing process Methods 0.000 title claims description 8
- 238000005498 polishing Methods 0.000 claims abstract description 31
- 238000000034 method Methods 0.000 claims abstract description 19
- 229910052751 metal Inorganic materials 0.000 claims abstract description 18
- 239000002184 metal Substances 0.000 claims abstract description 15
- 238000009825 accumulation Methods 0.000 claims abstract description 11
- 230000003746 surface roughness Effects 0.000 claims abstract description 11
- 239000000498 cooling water Substances 0.000 claims abstract description 10
- 239000012857 radioactive material Substances 0.000 claims abstract description 8
- 238000010438 heat treatment Methods 0.000 claims abstract description 7
- 238000005554 pickling Methods 0.000 claims abstract description 6
- 239000006104 solid solution Substances 0.000 claims abstract description 6
- 238000005260 corrosion Methods 0.000 claims description 12
- 230000007797 corrosion Effects 0.000 claims description 12
- 229910001220 stainless steel Inorganic materials 0.000 claims description 10
- 239000010935 stainless steel Substances 0.000 claims description 10
- 238000004140 cleaning Methods 0.000 claims description 4
- 239000000463 material Substances 0.000 abstract description 15
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Chemical compound O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract description 12
- 229910017052 cobalt Inorganic materials 0.000 abstract description 9
- 239000010941 cobalt Substances 0.000 abstract description 9
- GUTLYIVDDKVIGB-UHFFFAOYSA-N cobalt atom Chemical compound [Co] GUTLYIVDDKVIGB-UHFFFAOYSA-N 0.000 abstract description 9
- 239000000243 solution Substances 0.000 abstract description 3
- 239000012153 distilled water Substances 0.000 abstract description 2
- 229910000734 martensite Inorganic materials 0.000 abstract description 2
- 150000002739 metals Chemical class 0.000 abstract description 2
- 238000005406 washing Methods 0.000 abstract description 2
- 239000013078 crystal Substances 0.000 abstract 2
- 229910001566 austenite Inorganic materials 0.000 abstract 1
- VHFBTKQOIBRGQP-UHFFFAOYSA-N fluoro nitrate Chemical compound [O-][N+](=O)OF VHFBTKQOIBRGQP-UHFFFAOYSA-N 0.000 abstract 1
- 238000003754 machining Methods 0.000 abstract 1
- 238000007517 polishing process Methods 0.000 abstract 1
- 239000000941 radioactive substance Substances 0.000 description 9
- 230000000694 effects Effects 0.000 description 4
- PXHVJJICTQNCMI-UHFFFAOYSA-N nickel Substances [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 description 4
- 239000012925 reference material Substances 0.000 description 4
- 238000012360 testing method Methods 0.000 description 4
- 239000003082 abrasive agent Substances 0.000 description 3
- 238000009835 boiling Methods 0.000 description 3
- 230000000052 comparative effect Effects 0.000 description 3
- 238000010586 diagram Methods 0.000 description 3
- 238000005516 engineering process Methods 0.000 description 3
- 229910052759 nickel Inorganic materials 0.000 description 3
- 239000000126 substance Substances 0.000 description 3
- KRHYYFGTRYWZRS-UHFFFAOYSA-N Fluorane Chemical compound F KRHYYFGTRYWZRS-UHFFFAOYSA-N 0.000 description 2
- NBIIXXVUZAFLBC-UHFFFAOYSA-N Phosphoric acid Chemical compound OP(O)(O)=O NBIIXXVUZAFLBC-UHFFFAOYSA-N 0.000 description 2
- 239000007864 aqueous solution Substances 0.000 description 2
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 2
- 239000000470 constituent Substances 0.000 description 2
- 238000009499 grossing Methods 0.000 description 2
- 238000007654 immersion Methods 0.000 description 2
- 239000012535 impurity Substances 0.000 description 2
- 229910052760 oxygen Inorganic materials 0.000 description 2
- 239000001301 oxygen Substances 0.000 description 2
- 238000000746 purification Methods 0.000 description 2
- 238000011160 research Methods 0.000 description 2
- 235000019592 roughness Nutrition 0.000 description 2
- -1 Co2+ ions Chemical class 0.000 description 1
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 description 1
- 229910000831 Steel Inorganic materials 0.000 description 1
- 229910001347 Stellite Inorganic materials 0.000 description 1
- 238000010521 absorption reaction Methods 0.000 description 1
- 239000002253 acid Substances 0.000 description 1
- 238000005275 alloying Methods 0.000 description 1
- 229910000147 aluminium phosphate Inorganic materials 0.000 description 1
- 238000009390 chemical decontamination Methods 0.000 description 1
- 238000006243 chemical reaction Methods 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
- 238000005253 cladding Methods 0.000 description 1
- 238000005238 degreasing Methods 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 230000018109 developmental process Effects 0.000 description 1
- 238000005868 electrolysis reaction Methods 0.000 description 1
- 238000010828 elution Methods 0.000 description 1
- 238000011156 evaluation Methods 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 230000012447 hatching Effects 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 150000002500 ions Chemical class 0.000 description 1
- JEIPFZHSYJVQDO-UHFFFAOYSA-N iron(III) oxide Inorganic materials O=[Fe]O[Fe]=O JEIPFZHSYJVQDO-UHFFFAOYSA-N 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 150000001247 metal acetylides Chemical class 0.000 description 1
- 238000003801 milling Methods 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 238000005025 nuclear technology Methods 0.000 description 1
- YXJYBPXSEKMEEJ-UHFFFAOYSA-N phosphoric acid;sulfuric acid Chemical compound OP(O)(O)=O.OS(O)(=O)=O YXJYBPXSEKMEEJ-UHFFFAOYSA-N 0.000 description 1
- 239000002244 precipitate Substances 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
- 239000000047 product Substances 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 239000011347 resin Substances 0.000 description 1
- 229920005989 resin Polymers 0.000 description 1
- 238000001878 scanning electron micrograph Methods 0.000 description 1
- 238000005204 segregation Methods 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
- 239000010959 steel Substances 0.000 description 1
Classifications
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F16—ENGINEERING ELEMENTS AND UNITS; GENERAL MEASURES FOR PRODUCING AND MAINTAINING EFFECTIVE FUNCTIONING OF MACHINES OR INSTALLATIONS; THERMAL INSULATION IN GENERAL
- F16L—PIPES; JOINTS OR FITTINGS FOR PIPES; SUPPORTS FOR PIPES, CABLES OR PROTECTIVE TUBING; MEANS FOR THERMAL INSULATION IN GENERAL
- F16L58/00—Protection of pipes or pipe fittings against corrosion or incrustation
Landscapes
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- Mechanical Engineering (AREA)
- Protection Of Pipes Against Damage, Friction, And Corrosion (AREA)
- Rigid Pipes And Flexible Pipes (AREA)
Abstract
Description
【発明の詳細な説明】
〔産業上の利用分野〕
本発明は原子力プラント−次冷却水系に用いられるステ
ンレス鋼配管の製造法に係わる。DETAILED DESCRIPTION OF THE INVENTION [Industrial Field of Application] The present invention relates to a method of manufacturing stainless steel piping for use in nuclear power plant sub-cooling water systems.
原子力プラントの一次冷却水系に使用されている配管、
ポンプ、弁等はステンレス鋼及びステライト等（以下、
構成部材と略称する。）から構成されている。これらの
金属は長期間使用されると腐食損傷をうけ、構成金属元
素が原子炉冷却水（以下、冷却水と略称する。）中に溶
出し、原子炉内に持ち込まれる。溶出金属元素は大半が
酸化物となって燃料棒に付着し、中性子照射をうける。Piping used in the primary cooling water system of nuclear power plants,
Pumps, valves, etc. are made of stainless steel, Stellite, etc. (hereinafter referred to as
Abbreviated as component. ). When these metals are used for a long period of time, they are damaged by corrosion, and their constituent metal elements are eluted into reactor cooling water (hereinafter referred to as cooling water) and brought into the reactor. Most of the eluted metal elements become oxides and adhere to the fuel rods, where they are exposed to neutron irradiation.
ソノ結果、ＢＯｃｏ、ｌｌｌＩｃ０、”Ｃｒ 、 ”Ｍ
ｎ等の放射性核種が生成する。これらの放射性核種は
一次冷却水中に再溶出してイオンあるいは不溶性固体成
分（以下、クラッドと称する）として浮遊する。その一
部は炉水浄化用の脱塩器等で除去されるが、残りは一次
冷却水系を循環しているうちに構成部材表面に蓄積する
。このため、構成部材表面における線量率が高くなり、
保守・点検を実施する際の作業員の放射線被曝が問題と
なっている。Sono result, BOco, lllIc0, “Cr,”M
Radioactive nuclides such as n are generated. These radionuclides are re-eluted into the primary cooling water and suspended as ions or insoluble solid components (hereinafter referred to as cladding). A part of it is removed by a demineralizer for reactor water purification, but the rest accumulates on the surfaces of component parts while circulating in the primary cooling water system. Therefore, the dose rate on the surface of the component increases,
Radiation exposure of workers during maintenance and inspection has become a problem.
従って、放射性物質の付着量を低減させるため、その源
である前記金属元素の溶出を抑制する方法が提案されて
いる０例えば耐食性のよい材料の使用あるいは酸素を給
水系内に注入して構成部材の腐食を抑制する方法等があ
る。しかし、いずれの方法を用いても給水系をはじめと
し、−次冷却水系の構成部材の腐食を十分に抑制するこ
とはできず、−次冷却水中の放射性物質を十分に低減す
ることはできないため、構成部材への放射性物質の蓄積
による表面線量率の増加がやはり問題として残っている
。Therefore, in order to reduce the amount of radioactive substances attached, methods have been proposed to suppress the elution of the metal elements, which are the source of radioactive substances. For example, using materials with good corrosion resistance or injecting oxygen into the water supply system to There are methods for suppressing corrosion. However, no matter which method is used, it is not possible to sufficiently suppress corrosion of the constituent members of the sub-cooling water system, including the water supply system, and it is not possible to sufficiently reduce radioactive substances in the sub-cooling water. However, the increase in surface dose rate due to the accumulation of radioactive materials on components remains a problem.
また、構成部材に蓄積した放射性物質を除去する方法が
検討され、実施されている。現状では化学除染法が広く
用いられているが、この方法は酸溶液等の薬剤を用いて
化学反応により鋼表面の酸化皮膜を溶解し、同皮膜中に
存在する放射性物質を除去するものである。この方法の
問題は一時的に線量率を低減しても、構成部材を再び高
い濃度の放射性物質を溶解する液にさらした場合に急速
に再汚染されることである。Additionally, methods for removing radioactive substances accumulated in structural members are being studied and implemented. Currently, chemical decontamination methods are widely used, but this method uses chemicals such as acid solutions to dissolve the oxide film on the steel surface through a chemical reaction, and removes the radioactive substances present in the film. be. The problem with this method is that even if the dose rate is temporarily reduced, if the component is again exposed to a liquid that dissolves high concentrations of radioactive materials, it will quickly become recontaminated.
そこで、従事者被曝への寄与率の大きい炉回りステンレ
ス鋼配管を対象に、放射性物質の蓄積を抑制する技術の
開発が要望されている。従来、これに関する技術として
は、ステンレス鋼の接水面を電解研磨により平滑化する
方法がエレクトリック・パワー・リサーチ・インステイ
テユウト、エヌ・ピー３８３２号（１９８５年３月）
（ＥｌｅｃｔｒｉｃＰｏｗｅｒ Ｒｅ５ｅａｒｃｈ Ｉ
ｎ５ｔｉｔｕｔｅ、 Ｎ Ｐ −３８３２、Ｍａｒｃｈ
１９８５）において論じられている。Therefore, there is a need for the development of technology to suppress the accumulation of radioactive materials in the stainless steel piping surrounding the furnace, which has a large contribution to radiation exposure among workers. Conventionally, as a technique related to this, a method of smoothing the water contact surface of stainless steel by electrolytic polishing was published in Electric Power Research Institute, NP No. 3832 (March 1985).
(ElectricPower Research I
n5 titute, NP-3832, March
1985).
上記従来技術は、対象とするステンレス鋼配管内部に７
５〜９０℃に加温したリン酸水溶液を満たし、陰極を挿
入し、配管自体を陽極として数分間から数１０分間、電
解研摩を行なうものである。The above conventional technology has 7 parts inside the target stainless steel pipe.
It is filled with a phosphoric acid aqueous solution heated to 5 to 90°C, a cathode is inserted, and electrolytic polishing is performed for several minutes to several tens of minutes using the pipe itself as an anode.
この技術の問題は、研摩面の状態が被研摩材の材質にき
わめて影響を受けやすいことにある。すなわち、単に金
属の種類のみならず、不純物の種類、量、合金添加元素
の種類、量及び熱処理、加工度の影響を受け、研摩条件
以外に浴組成をも変えなくてはならない場合が多い。ま
た、微小凸部を溶解する方法であるため、比較的大きな
粗さ、きす、あるいは製造工程で生ずるパーティングラ
イン等を除去することは困難である。したがって、一般
にこの研摩法を用いる場合には、あらかじめ機械研摩に
よって平滑化しておく必要がある。さらに被研摩材表面
に付着しているさび、油脂、汚れなどは研摩に悪い影響
を与えるので、酸洗、脱脂。The problem with this technique is that the condition of the polished surface is extremely sensitive to the material of the material being polished. That is, it is often necessary to change not only the polishing conditions but also the bath composition, which is affected not only by the type of metal but also by the type and amount of impurities, the type and amount of alloying elements, heat treatment, and degree of processing. Furthermore, since the method involves dissolving minute convex portions, it is difficult to remove relatively large roughness, scratches, or parting lines that occur during the manufacturing process. Therefore, when using this polishing method, it is generally necessary to smooth the surface by mechanical polishing in advance. Furthermore, rust, oil, dirt, etc. adhering to the surface of the material to be polished have a negative effect on polishing, so pickling and degreasing are necessary.
洗浄はとくに厳重に行なう必要がある。こうした問題は
工業的には作業の繁雑さを招いている。Cleaning must be particularly rigorous. These problems make industrial work complicated.
本発明の目的は、電解研摩によらず放射性物質の蓄積の
小さい金属面を得ることにある。An object of the present invention is to obtain a metal surface with less accumulation of radioactive substances without electrolytic polishing.
上記目的は、ステンレス鋼配管の製造工程において、固
溶体熱処理後、酸洗、洗浄したのち、金属結晶粒界が露
出せず、かつ表面粗さが６ｓ以下となるように機械研摩
を行なうことにより、達成される。The above purpose is to perform mechanical polishing in the manufacturing process of stainless steel piping after solid solution heat treatment, pickling, and cleaning so that metal grain boundaries are not exposed and the surface roughness is 6s or less. achieved.
線量上昇に寄与する放射性核種としては、半減期が５．
２６年を長く、またγ線の崩壊エネルギーが大きい８０
ＣＯが代表的なものである。このｅＯＣＯのステンレ
ス鋼への蓄積量は、腐食にともなって形成される酸化被
膜量にほぼ比例することが、ニュークリア・テクノロジ
ー、６４巻（１９８４年）第３５頁から第４２頁（Ｎｕ
ｃｌｅａｒ Ｔａｃｈ、ｎｏｌｏｇｙ。The radionuclides that contribute to the dose increase have a half-life of 5.
26 years is long, and the decay energy of gamma rays is large80
CO is a typical example. Nuclear Technology, Vol. 64 (1984), pp. 35 to 42, states that the amount of eOCO accumulated on stainless steel is approximately proportional to the amount of oxide film formed as a result of corrosion.
clear touch, nology.
Ｖｏｌ、６４ （１９８４） ｐｐ３５−４２）等で知
られている。したがって、放射性物質の蓄積を抑制する
ためには、金属表面を平滑化することにより接木実効表
面積を減少することが有効と考えられている。この手段
としては、機械研摩、化学研摩、電解研摩が考えられる
が、電解研摩には前述した問題がある。また、この問題
は化学研摩についても同じである。さらにこの２つの研
摩を行った場合、金属表面には結晶粒界が露出するが１
粒界には（ｉ）炭化物その他の相が析出すること、及び
（ｉｔ）不純物偏析があることから腐食を生じやすい。Vol. 64 (1984) pp35-42). Therefore, in order to suppress the accumulation of radioactive substances, it is considered effective to reduce the effective surface area of the graft by smoothing the metal surface. Possible means for this include mechanical polishing, chemical polishing, and electrolytic polishing, but electrolytic polishing has the aforementioned problems. This problem also applies to chemical polishing. Furthermore, when these two types of polishing are performed, grain boundaries are exposed on the metal surface, but 1
Corrosion tends to occur at grain boundaries because (i) carbides and other phases precipitate, and (it) there is segregation of impurities.
一方、機械研摩を行うと、結晶粒界を金属表面から消失
することができる。しかしながら、５ＵＳ３０４等の準
安定系オーステナイト組織では強度の機械研摩により、
加工誘起マルテンサイトを生じ、耐食性が悪くなる。そ
のため酸化被膜の形成量も多くなり、コバルト同位元素
をはじめとする放射性物質の蓄積量も増す。本発明では
ＳＵＳ ３１６及び３１６Ｌは安定系オーステナイト組
織であるため１機械研摩により加工誘起マルテンサイド
を生ずることはなく、また表面粗さ、６ｓ（表面の最大
高さ、６μｍ）以下で酸化皮膜の成長及びそれにともな
うコバルトの？５Ｍが著しく抑制されることを見出した
。そこで、ステンレス鋼配管の製造工程において、固溶
体熱処理後。On the other hand, mechanical polishing can eliminate grain boundaries from the metal surface. However, in metastable austenitic structures such as 5US304, intense mechanical polishing
Forms deformation-induced martensite, resulting in poor corrosion resistance. As a result, the amount of oxide film formed increases, and the amount of radioactive substances including cobalt isotopes accumulated also increases. In the present invention, since SUS 316 and 316L have a stable austenitic structure, mechanical polishing will not cause deformation-induced martenside, and the growth of an oxide film will occur when the surface roughness is less than 6s (maximum height of the surface, 6 μm). and cobalt associated with it? It was found that 5M was significantly suppressed. Therefore, in the manufacturing process of stainless steel piping, after solid solution heat treatment.
酸洗、洗浄したのち、金属結晶粒界が露出せず、かつ表
面粗さが６ｓ以下となるように機械研摩を行なうことに
より、腐食と放射性物質の蓄積を抑制しうる配管を提給
することができる。After pickling and cleaning, mechanical polishing is performed so that metal grain boundaries are not exposed and the surface roughness is 6s or less, thereby providing piping that can suppress corrosion and accumulation of radioactive materials. I can do it.
以下１本発明の実施例について説明する。 An embodiment of the present invention will be described below.
実施例１
固溶体熱処理した５ＵＳ３１６Ｌ製配管の内面を硝フッ
酸水溶液により酸洗し１次いで蒸留水で十分に洗浄した
ものを基準材１とした。次いで、フラッパー研摩により
１表面粗さが異なる６種類の配管２を作成した。粗さの
範囲は３．９ｓ〜２０．５３である。Example 1 Reference material 1 was prepared by pickling the inner surface of a 5US316L pipe that had been subjected to solid solution heat treatment with an aqueous solution of nitric and hydrofluoric acid, and then thoroughly washing it with distilled water. Next, six types of piping 2 with different surface roughnesses were created by flapper polishing. The roughness range is 3.9s to 20.53.
また、フラッパー研摩により作成した６、ＯＳ及び３．
９８の２種類の配管にリン酸−硫酸水溶液中で電解研摩
を行い、各々３．６Ｓ及び１．９Ｓの２種類の配管を作
成し、比較材３とした。試験片は各配管の内面から厚さ
１ｍｍの層を切断し、１０１０Ｘ３０の板状に成形した
ものを使用した。In addition, 6, OS and 3. were created by flapper polishing.
Two types of piping of No. 98 were electrolytically polished in an aqueous phosphoric acid-sulfuric acid solution to create two types of piping of 3.6S and 1.9S, respectively, and were used as comparative material 3. The test piece used was a layer having a thickness of 1 mm cut from the inner surface of each pipe and formed into a 1010×30 plate shape.
コバルト蓄積評価試験は前記試験片をＣｏ２＋イオンを
０．０５〜３ 、０ ｐｐｂ含む２８８℃の流動純水中
に１０００時間まで浸漬することにより行った。溶存酸
素濃度は１５０〜２５０ｐｐｂであった。The cobalt accumulation evaluation test was conducted by immersing the test piece in flowing pure water at 288°C containing 0.05 to 3.0 ppb of Co2+ ions for up to 1000 hours. Dissolved oxygen concentration was 150-250 ppb.
浸漬後、配管内表面以外を樹脂でコーティングしたのち
、カソード電解法により皮膜を剥離し、溶解し、原子吸
光法によりＣ０１Ｆｅ、Ｎｉ及びＣｒの量を求める。After immersion, the area other than the inner surface of the pipe is coated with resin, and then the film is peeled off by cathodic electrolysis and dissolved, and the amounts of C01Fe, Ni, and Cr are determined by atomic absorption method.
第１図にコバルト蓄積量を、第２図に皮膜量を示した。Figure 1 shows the amount of cobalt accumulated, and Figure 2 shows the amount of film.
なお、皮膜量はＧｏ−Ｆｅ、Ｎｉ及びＣｒの総和量とし
て求めた。表面粗さが６．Ｏ５以下にフラッパー研摩し
た材料２でコバルト蓄積量は最小となり、電解研摩した
比較材３と同程度の蓄積量を示した。皮膜量も同じ傾向
を示し、腐食も６．０ ｓ 以下で最も抑制されるこ
とがわかった。In addition, the film amount was calculated|required as the total amount of Go-Fe, Ni, and Cr. Surface roughness is 6. Material 2, which was flapper-polished to O5 or lower, had the lowest amount of cobalt accumulated, and the amount of cobalt accumulated was comparable to Comparative Material 3, which was electrolytically polished. It was found that the amount of film showed the same tendency, and corrosion was most suppressed at 6.0 s or less.
第３図に、浸漬試験後の金属表面を走査型電子ｉ微鏡で
調べた結果を示した。基準材では金属結晶粒界が残って
いる。フラッパー研摩により、表面粗さを６．０３ に
した材料では金属結晶粒界が消失し、表面が皮膜で一様
におおわれており、耐食性が向上していることを示して
いる。Figure 3 shows the results of examining the metal surface after the immersion test using a scanning electronic i-microscope. In the reference material, metal grain boundaries remain. In the material whose surface roughness was set to 6.03 by flapper polishing, the metal grain boundaries disappeared and the surface was uniformly covered with a film, indicating improved corrosion resistance.
なお、ＳＵＳ ３１８テも５ＵＳ３１６Ｌと同様の結果
が得られたが、５ＵＳ３０４ではフラッパー研摩材２へ
のコバルト蓄積量及び皮膜量が基準材１よりも浸漬１０
００時間後において多くなることを認めた。In addition, the same results as 5US316L were obtained for SUS 318TE, but in 5US304, the amount of cobalt accumulated and the amount of film on flapper abrasive material 2 were lower than that of reference material 1.
It was observed that the amount increased after 00 hours.
実施例２
機械研摩法として、フラッパー研摩以外に、ヤスリ仕上
、フライス、施盤、中グリ、ブローチ、シェービング、
グラインダー研摩、ホーニング、ペーパ仕上、ブラシ研
摩などがあるが、いずれの方法によってもフラッパー研
摩と同様の効果が得られた。Example 2 Mechanical polishing methods include, in addition to flapper polishing, filing, milling, lathing, boring, broaching, shaving,
There are grinder polishing, honing, paper finishing, brush polishing, etc., and the same effect as flapper polishing was obtained with each method.
実施例３
本発明に基づいて製造した配管の通用範囲を沸騰水型原
子力プラントを例にとって示す。第４図に再循環系配管
構成と適用場所をハツチングで示した。なお、再循環系
配管のみならず、炉浄化系配管への適用も可能である。Example 3 The scope of application of piping manufactured based on the present invention will be illustrated by taking a boiling water nuclear power plant as an example. Figure 4 shows the recirculation system piping configuration and application locations with hatching. Note that the present invention can be applied not only to recirculation system piping but also to furnace purification system piping.
実施例４
原子力プラントはいく種類もあるが、本発明はそれらの
いずれにも適用することができる。たとえば、加圧水型
プラントでは一次系構造材等である。Example 4 There are many types of nuclear power plants, and the present invention can be applied to any of them. For example, in a pressurized water plant, it is a primary structural material.
実施例５
本発明は炉回り配管への放射性物質の蓄積抑制を主対象
としているが、沸騰水型プラントの給水ヒータチューブ
等に対して適用した場合には、コバルト及びニッケル等
の腐食生成物の放出を抑制することができる。Example 5 The present invention is mainly aimed at suppressing the accumulation of radioactive materials in piping around the reactor, but when applied to feed water heater tubes of boiling water plants, it is possible to prevent corrosion products such as cobalt and nickel. Release can be suppressed.
以上の説明から明らがなように１本発明は簡便な手段に
よってプラント構成部材への放射性物質の蓄積を抑制で
きる。また、その応用範囲も広く、特に原子力プラント
において従事者の被爆を低減するのに好適であり、実用
価値が高く、工業的にきわめて有意義なものである。As is clear from the above description, the present invention can suppress the accumulation of radioactive substances in plant components by simple means. Moreover, its application range is wide, and it is particularly suitable for reducing the radiation exposure of workers in nuclear power plants, has high practical value, and is extremely significant industrially.
第１図はｃｏ蓄積量を表面粗さの関係図、第２図は皮膜
量と表面粗さの関係図、第３図は本発明法の金属組織を
示す走査型電子顕微鏡写真、第４図は沸騰水型原子力プ
ラント再循環系配管の構成図である。
符号の説明
１・・・基準材、２・・・フラッパー研摩材、３・・・
電解研摩材（比較材）、４・・・直管、５・・・直管付
１字管。
６・・・曲管、７・・・異径クロス、８・・・圧力容器
。Figure 1 is a relationship diagram between the amount of Co accumulated and surface roughness, Figure 2 is a relationship diagram between film amount and surface roughness, Figure 3 is a scanning electron micrograph showing the metal structure of the method of the present invention, and Figure 4 1 is a configuration diagram of a boiling water nuclear power plant recirculation system piping. Explanation of symbols 1... Reference material, 2... Flapper abrasive material, 3...
Electrolytic abrasive material (comparative material), 4...straight pipe, 5...1-shaped pipe with straight pipe. 6...Bent pipe, 7...Different diameter cross, 8...Pressure vessel.
Claims (1)
ント用ステンレス鋼配管の腐食と放射性物質の蓄積を抑
制するに当り、該配管の製造工程において、固溶体熱処
理後、酸洗、洗浄したのち、金属結晶粒界が露出せず、
かつ表面粗さが６ｓ以下となるように機械研磨を行なう
ことを特徴とする原子力プラント配管の製造法。 ２、前記ステンレス鋼はＳＵＳ３１６及びＳＵＳ３１６
Ｌであることを特徴とする特許請求の範囲第１項記載の
原子力プラント配管の製造法。[Claims] 1. In order to suppress the corrosion and accumulation of radioactive materials in stainless steel piping for nuclear power plants that comes into contact with reactor cooling water containing radioactive materials, pickling is performed after solid solution heat treatment in the manufacturing process of the piping. , after cleaning, metal grain boundaries are not exposed,
A method for manufacturing nuclear power plant piping, characterized in that mechanical polishing is performed so that the surface roughness is 6s or less. 2. The stainless steel is SUS316 and SUS316
The method for manufacturing nuclear power plant piping according to claim 1, wherein the piping is L.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2012986A JPS62181834A (en) | 1986-02-03 | 1986-02-03 | Manufacturing method for pipe used in nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2012986A JPS62181834A (en) | 1986-02-03 | 1986-02-03 | Manufacturing method for pipe used in nuclear power plant |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS62181834A true JPS62181834A (en) | 1987-08-10 |
| JPH0451288B2 JPH0451288B2 (en) | 1992-08-18 |
Family
ID=12018518
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP2012986A Granted JPS62181834A (en) | 1986-02-03 | 1986-02-03 | Manufacturing method for pipe used in nuclear power plant |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS62181834A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP5029788B1 (en) * | 2011-11-18 | 2012-09-19 | 住友金属工業株式会社 | Austenitic stainless steel |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS59126997A (en) * | 1983-01-12 | 1984-07-21 | 株式会社日立製作所 | Atomic power plant |
-
1986
- 1986-02-03 JP JP2012986A patent/JPS62181834A/en active Granted
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS59126997A (en) * | 1983-01-12 | 1984-07-21 | 株式会社日立製作所 | Atomic power plant |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP5029788B1 (en) * | 2011-11-18 | 2012-09-19 | 住友金属工業株式会社 | Austenitic stainless steel |
| WO2013073055A1 (en) * | 2011-11-18 | 2013-05-23 | 住友金属工業株式会社 | Austenitic stainless steel |
| KR101393784B1 (en) * | 2011-11-18 | 2014-05-12 | 신닛테츠스미킨 카부시키카이샤 | Austenitic stainless steel |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0451288B2 (en) | 1992-08-18 |
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