JPS6115950B2 - - Google Patents
Info
- Publication number
- JPS6115950B2 JPS6115950B2 JP12232180A JP12232180A JPS6115950B2 JP S6115950 B2 JPS6115950 B2 JP S6115950B2 JP 12232180 A JP12232180 A JP 12232180A JP 12232180 A JP12232180 A JP 12232180A JP S6115950 B2 JPS6115950 B2 JP S6115950B2
- Authority
- JP
- Japan
- Prior art keywords
- zirconium
- nodular
- corrosion
- nodular corrosion
- diffusion layer
- 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
- 230000007797 corrosion Effects 0.000 claims description 34
- 238000005260 corrosion Methods 0.000 claims description 34
- 229910001093 Zr alloy Inorganic materials 0.000 claims description 23
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 claims description 16
- 239000001301 oxygen Substances 0.000 claims description 16
- 229910052760 oxygen Inorganic materials 0.000 claims description 16
- 229910045601 alloy Inorganic materials 0.000 claims description 13
- 239000000956 alloy Substances 0.000 claims description 13
- 238000009792 diffusion process Methods 0.000 claims description 12
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 claims description 10
- 229910052726 zirconium Inorganic materials 0.000 claims description 10
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 claims description 8
- PXHVJJICTQNCMI-UHFFFAOYSA-N Nickel Chemical compound [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 claims description 6
- 238000004519 manufacturing process Methods 0.000 claims description 5
- 229910052742 iron Inorganic materials 0.000 claims description 4
- VYZAMTAEIAYCRO-UHFFFAOYSA-N Chromium Chemical compound [Cr] VYZAMTAEIAYCRO-UHFFFAOYSA-N 0.000 claims description 3
- ATJFFYVFTNAWJD-UHFFFAOYSA-N Tin Chemical compound [Sn] ATJFFYVFTNAWJD-UHFFFAOYSA-N 0.000 claims description 3
- 229910052804 chromium Inorganic materials 0.000 claims description 3
- 239000011651 chromium Substances 0.000 claims description 3
- 238000000034 method Methods 0.000 claims description 3
- 229910052759 nickel Inorganic materials 0.000 claims description 3
- 239000000758 substrate Substances 0.000 claims 1
- 239000001257 hydrogen Substances 0.000 description 10
- 229910052739 hydrogen Inorganic materials 0.000 description 10
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 9
- 239000011162 core material Substances 0.000 description 6
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 6
- 238000004458 analytical method Methods 0.000 description 5
- 238000005253 cladding Methods 0.000 description 5
- 239000000446 fuel Substances 0.000 description 5
- 239000000463 material Substances 0.000 description 5
- 238000006243 chemical reaction Methods 0.000 description 4
- 150000004678 hydrides Chemical class 0.000 description 3
- 238000009835 boiling Methods 0.000 description 2
- 239000004020 conductor Substances 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 229910003460 diamond Inorganic materials 0.000 description 2
- 239000010432 diamond Substances 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 239000000203 mixture Substances 0.000 description 2
- 239000000843 powder Substances 0.000 description 2
- 238000005482 strain hardening Methods 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- 238000004566 IR spectroscopy Methods 0.000 description 1
- 229910020900 Sn-Fe Inorganic materials 0.000 description 1
- 229910019314 Sn—Fe Inorganic materials 0.000 description 1
- 238000000137 annealing Methods 0.000 description 1
- 230000015572 biosynthetic process Effects 0.000 description 1
- 239000011248 coating agent Substances 0.000 description 1
- 238000000576 coating method Methods 0.000 description 1
- 239000013078 crystal Substances 0.000 description 1
- 238000002474 experimental method Methods 0.000 description 1
- 150000002431 hydrogen Chemical class 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 150000002739 metals Chemical class 0.000 description 1
- 238000001000 micrograph Methods 0.000 description 1
- 229910052758 niobium Inorganic materials 0.000 description 1
- 230000003287 optical effect Effects 0.000 description 1
- 230000003647 oxidation Effects 0.000 description 1
- 238000007254 oxidation reaction Methods 0.000 description 1
- 239000002245 particle Substances 0.000 description 1
- 230000000149 penetrating effect Effects 0.000 description 1
- 238000005498 polishing Methods 0.000 description 1
- 238000004445 quantitative analysis Methods 0.000 description 1
Classifications
-
- C—CHEMISTRY; METALLURGY
- C23—COATING METALLIC MATERIAL; COATING MATERIAL WITH METALLIC MATERIAL; CHEMICAL SURFACE TREATMENT; DIFFUSION TREATMENT OF METALLIC MATERIAL; COATING BY VACUUM EVAPORATION, BY SPUTTERING, BY ION IMPLANTATION OR BY CHEMICAL VAPOUR DEPOSITION, IN GENERAL; INHIBITING CORROSION OF METALLIC MATERIAL OR INCRUSTATION IN GENERAL
- C23C—COATING METALLIC MATERIAL; COATING MATERIAL WITH METALLIC MATERIAL; SURFACE TREATMENT OF METALLIC MATERIAL BY DIFFUSION INTO THE SURFACE, BY CHEMICAL CONVERSION OR SUBSTITUTION; COATING BY VACUUM EVAPORATION, BY SPUTTERING, BY ION IMPLANTATION OR BY CHEMICAL VAPOUR DEPOSITION, IN GENERAL
- C23C8/00—Solid state diffusion of only non-metal elements into metallic material surfaces; Chemical surface treatment of metallic material by reaction of the surface with a reactive gas, leaving reaction products of surface material in the coating, e.g. conversion coatings, passivation of metals
- C23C8/06—Solid state diffusion of only non-metal elements into metallic material surfaces; Chemical surface treatment of metallic material by reaction of the surface with a reactive gas, leaving reaction products of surface material in the coating, e.g. conversion coatings, passivation of metals using gases
- C23C8/08—Solid state diffusion of only non-metal elements into metallic material surfaces; Chemical surface treatment of metallic material by reaction of the surface with a reactive gas, leaving reaction products of surface material in the coating, e.g. conversion coatings, passivation of metals using gases only one element being applied
- C23C8/10—Oxidising
- C23C8/12—Oxidising using elemental oxygen or ozone
Landscapes
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Engineering & Computer Science (AREA)
- Materials Engineering (AREA)
- Mechanical Engineering (AREA)
- Metallurgy (AREA)
- Organic Chemistry (AREA)
- Powder Metallurgy (AREA)
- Physical Vapour Deposition (AREA)
Description
【発明の詳細な説明】
本発明は耐ノジユラーコロージヨン性のすぐれ
たジルコニウム合金およびその製造方法に関す
る。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a zirconium alloy with excellent nodular corrosion resistance and a method for producing the same.
例えば沸騰水型軽水炉においては、燃料被覆管
や、チヤンネルボツクスなどの構造材料として、
ジルカロイ―２、ジルカロイ―４などと呼称され
るジルコニウム合金が使用されている。即ち燃料
被覆管やチヤンネルボツクスなど、所謂る炉心構
造物については、中性子経済および高温における
耐食性の点から、通常ASTM規格G2―74もしく
はB353―77aによる耐食性試験に合格したジルコ
ニウム合金が実用に供されている。ところで上記
ジルコニウム合金から構成された炉心構造物につ
いてみると、実装運転において、ノジユラーコロ
ージヨンと呼ばれる腐食反応による斑点状の白色
生成物が構造物表面に生成する。上記白色腐食生
成物は、ノジユラーコロージヨンの進展に伴ない
次第に成長して、時には剥落することもあり、ま
たこの剥落による肉減りは、チヤンネルボツクス
や燃料被覆管などの炉心構造物の機械的強度の低
下を招来する恐れがある。炉心構造物についての
より安全性乃至信頼性の点から、上記耐ノジユラ
ーコロージヨン性は注目されており、ジルコニウ
ム合金からなる構造物の表面に電子伝導性材料層
を薄く被覆することも試みられている。（特開昭
52―5629号）。しかしこの電子伝導性材料の被覆
によるノジユラーコロージヨンの発生防止或いは
軽減（耐ノジユラーコロージヨン性付与）手段は
異種金属との共存、接触腐食などの点から充分な
手段とは言い難い。 For example, in boiling water reactors, it is used as a structural material for fuel cladding tubes and channel boxes.
Zirconium alloys called Zircaloy-2, Zircaloy-4, etc. are used. In other words, for so-called reactor core structures such as fuel cladding tubes and channel boxes, zirconium alloys that have passed the corrosion resistance test according to ASTM standard G2-74 or B353-77a are usually put into practical use from the viewpoint of neutron economy and corrosion resistance at high temperatures. ing. By the way, regarding a core structure made of the above-mentioned zirconium alloy, during mounting operation, speckled white products due to a corrosion reaction called nodular corrosion are generated on the surface of the structure. The above-mentioned white corrosion products gradually grow as nodular corrosion progresses and sometimes flake off, and the thinning caused by this flaking is caused by mechanical damage to core structures such as channel boxes and fuel cladding. This may lead to a decrease in strength. The nodular corrosion resistance described above has been attracting attention from the standpoint of safety and reliability for core structures, and attempts have also been made to coat the surface of structures made of zirconium alloys with a thin layer of electronically conductive material. ing. (Tokukai Akira
52-5629). However, this means of preventing or reducing the occurrence of nodular corrosion (providing nodular corrosion resistance) by coating with an electron conductive material is not a sufficient means in view of coexistence with dissimilar metals, contact corrosion, and the like.
本発明は上記事情に鑑みなされたもので、チヤ
ンネルボツクス、燃料被覆管など炉心材に適する
耐ノジユラーコロージヨン性のすぐれたジルコニ
ウム合金と、その製造方法を提供しようとするも
のである。 The present invention has been made in view of the above circumstances, and it is an object of the present invention to provide a zirconium alloy with excellent nodular corrosion resistance suitable for core materials such as channel boxes and fuel cladding tubes, and a method for producing the same.
即ち、本発明者らは、上記ジルコニウム合金に
おけるノジユラーコロージヨンの主要反応がジル
コニウム合金内部での水素化物生成反応であるこ
とを見出し、また合金表面近傍に酸素の拡散層を
形成しておくとこの拡散層が水素の耐ノジユラー
コロージヨン性の向上に寄与することに着目して
なされたものである。 That is, the present inventors have discovered that the main reaction of nodular collosis in the above-mentioned zirconium alloy is a hydride production reaction within the zirconium alloy, and that by forming an oxygen diffusion layer near the alloy surface. This was done with the focus on the fact that this diffusion layer contributes to improving the nodular corrosion resistance of hydrogen.
以下にその詳細を説明する。 The details will be explained below.
先ずチヤンネルボツクスを構成するジルコニウ
ム合金片（27mm×20mm×３mm）を用意し、粒径約
25μｍのダイヤモンド粉で表面研摩後、500℃、
107Kg／cm2の水蒸気環境中に保持した。尚この試
験環境は、290℃、76Kg／cm2の沸騰水雰囲気で且
つ中性子照射の影響を考慮した実炉環境を模擬し
たノジユラーコロージヨンの加速試験である。 First, prepare the zirconium alloy pieces (27 mm x 20 mm x 3 mm) that will make up the channel box, and
After surface polishing with 25μm diamond powder, 500℃,
It was maintained in a water vapor environment of 107 Kg/cm 2 . This test environment is an accelerated nodular corrosion test that simulates the actual reactor environment in a boiling water atmosphere of 290°C and 76 kg/cm 2 and taking into account the effects of neutron irradiation.
上記試験において、数時間経過で、表面に斑点
状の白色生成物が発生し時間とともに次第に大き
く生成した。第１図ａに40時間保持後における表
面状態を写真で示し、また試験片の重量変化（腐
食量）の傾向を第２図に曲線ａで示す如くであつ
た。しかして上記試験片の表面に発生した白色生
成物を剥離回収して赤外線吸収分光およびＸ線結
晶解析により構造や組成など調べたところ単斜晶
系のZrO2であつた。一方ジルコニウム合金に対
する水の影響など調べるため前記ノジユラーコロ
ージヨン性加速試験において、試験片に含有され
ている酸素および水素の定量分析を行なつた。尚
この両成分の分析においては試験片表面の酸化生
成物を除去した後分析に供した。上記分析の結
果、腐食の進行に伴ない酸素含有量はほとんど変
化しないが水素の含有量は第３図に曲線ａで示す
如く腐食進行に伴ない著しく増大している。この
水素含有量の増大は試験片と水との反応で（ノジ
ユラーコロージヨンによつて）副生する水素が試
験片内部にほとんど吸収されることを示す。 In the above test, speckled white products were generated on the surface after several hours and gradually became larger over time. Fig. 1a shows a photograph of the surface condition after 40 hours of holding, and Fig. 2 shows the tendency of weight change (corrosion amount) as shown by curve a. However, the white product generated on the surface of the test piece was peeled off and collected, and its structure and composition were investigated by infrared absorption spectroscopy and X-ray crystal analysis, and it was found to be monoclinic ZrO 2 . On the other hand, in order to investigate the effects of water on the zirconium alloy, quantitative analysis of oxygen and hydrogen contained in the test pieces was conducted in the accelerated nodular corrosion test. In the analysis of these two components, the oxidation products on the surface of the test piece were removed before the analysis. As a result of the above analysis, the oxygen content hardly changes as the corrosion progresses, but the hydrogen content increases significantly as the corrosion progresses, as shown by curve a in FIG. This increase in hydrogen content indicates that most of the hydrogen produced by the reaction between the test piece and water (due to nodular collage) is absorbed inside the test piece.
さらに上記吸収された水素の状態を知るため
に、試験40時間後、試験片の内部組織を光学顕微
鏡によつて観察したところ第４図ａに示す如く、
水素化物ZrHxに帰属する黒色物質がほぼ均一に
（表面近傍を含め全体的に）分布していた。 Furthermore, in order to understand the state of the absorbed hydrogen, the internal structure of the test piece was observed using an optical microscope after 40 hours of the test, as shown in Figure 4a.
The black substance belonging to the hydride ZrHx was almost uniformly distributed (over the entire surface including near the surface).
上記実験事実からジルコニウム合金のノジユラ
ーコロージヨンは次の化学式で推論付けられる。 From the above experimental facts, the nodular collosis of zirconium alloy can be deduced from the following chemical formula.
（１＋４／ｘ）Zr＋2H2O→ZrO2＋４／ｘZrHx
従つて何らかの手段により、ジルコニウム合金
の内部に水素が侵入するのを防ぎ、ZrHxの生成
を防止乃至抑制し得ればノジユラーコロージヨン
の発生を阻止乃至軽減し得ることになる。 ( 1 + 4 / can be prevented or reduced.
本発明はこのような実験、解析に基づきなされ
たもので、ジルコニウム合金、例えば錫１〜1.8
％、鉄0.1〜0.2％、必要に応じニツケル0.1％以
下、クロム0.2％以下（重量％）および残部がジ
ルコニウムからなる合金の表面近傍に厚さ１μｍ
〜１mm程度の酸素拡散層を形成し、この拡散層で
水素の内部侵入を防止することによつて、すぐれ
た耐ノジユラーコロージヨン性を発揮させるもの
である。 The present invention has been made based on such experiments and analysis.
%, 0.1 to 0.2% iron, 0.1% or less nickel if necessary, 0.2% chromium or less (wt%), and the balance zirconium in a thickness of 1 μm near the surface.
By forming an oxygen diffusion layer of approximately 1 mm in thickness and preventing hydrogen from penetrating inside, excellent nodular corrosion resistance is exhibited.
しかしてこのような本発明に係る耐ノジユラー
コロージヨン性ジルコニウム合金は次のような手
段によつて容易に製造しうる。即ちジルコニウム
合金例えば上記組成のジルコニウム合金を500〜
1000℃の温度で、１×10-3mmHg〜１×104mmHgの
酸素雰囲気下、１〜８時間放置することにより表
面近傍に酸素拡散層の形成されて成る耐ノジユラ
ーコロージヨン性ジルコニウム合金が得られる。
この製造方法乃至処理方法において、温度を500
〜1000℃に選んだのは、500℃以下では所要の酸
素拡散層が形成し難く、また1000℃を超えると合
金構造において粒径の粗大化などにより機械的強
度の低下を招来する傾向が認められるためであ
る。好しくは上記酸素拡散処理は、最終的な冷間
加工前に行なえば、その後の冷間加工、歪取り焼
純においても形成された酸素拡散層がそのまま残
存して所要の耐ノジユラーコロージヨン性を発揮
する。またここで雰囲気につき酸素１×10-3mm
Hgから１×104mmHgの範囲としたのはこの範囲
外では所要の酸素拡散層を形成し難たかつたり、
或いは経済的にかえつて不利だつたりするからで
ある。 However, the nodular corrosion-resistant zirconium alloy according to the present invention can be easily produced by the following method. That is, a zirconium alloy, for example, a zirconium alloy having the above composition,
A nodular corrosion-resistant zirconium alloy in which an oxygen diffusion layer is formed near the surface by leaving it for 1 to 8 hours at a temperature of 1000°C in an oxygen atmosphere of 1 × 10 -3 mmHg to 1 × 10 4 mmHg. is obtained.
In this manufacturing method or treatment method, the temperature is
~1000℃ was chosen because it is difficult to form the required oxygen diffusion layer below 500℃, and when the temperature exceeds 1000℃, the grain size tends to coarsen in the alloy structure, resulting in a decrease in mechanical strength. This is so that you can be saved. Preferably, if the above oxygen diffusion treatment is performed before the final cold working, the formed oxygen diffusion layer remains as it is even during subsequent cold working and strain relief annealing, thereby providing the required nodular corrosion resistance. Demonstrate your sexuality. Also here, oxygen per atmosphere is 1×10 -3 mm
The reason for setting the range from Hg to 1×10 4 mmHg is that outside this range it is difficult to form the required oxygen diffusion layer.
Or it may even be economically disadvantageous.
次にこのような本発明に係る耐ノジユラーコロ
ージヨン性ジルコニウム合金の諸特性などを具体
的に示す。例えば重量比で錫１〜1.8％、鉄0.1〜
0.2％、ニツケル0.1％以下、クロム0.2％以下、残
部ジルコニウムから成るジルコニウム合金片（27
mm×20mm×３mm）を用意し、この合金片の表面を
平均粒径約25μｍのダイヤモンド粉で研摩したも
のを試験片として次のような試験を行なつた。即
ち500℃、107Kg／cm2の水蒸気環境中に保持して、
試験片表面の状態変化、試験片の腐食による重量
変化（腐食量）、試験片中の水素含有量変化、お
よび試験片の内部組織の観察など行なつた。この
試験によると、保持時間40時間後における表面状
態は第１図ｂに示す如く白色生成物の発生は全く
認められず、腐食量も第２図にて曲線ｂで示す如
くほとんど増量せずすぐれた耐ノジユラーコロー
ジヨン性を備えている。一方上述の如くノジユラ
ーコロージヨン性に関係する水素の含有量も第３
図にて曲線ｂで示すようにほとんど増量が認めら
れず、また内部組織においても、水素化物ZrHx
に帰属される黒色物質の量も著しく少量であつ
た。 Next, various properties of the nodular corrosion-resistant zirconium alloy according to the present invention will be specifically shown. For example, tin 1~1.8%, iron 0.1~
Zirconium alloy piece (27
mm x 20 mm x 3 mm) was prepared, and the surface of this alloy piece was polished with diamond powder having an average particle size of about 25 μm, and the following tests were conducted using the test piece as a test piece. That is, maintained in a water vapor environment of 500℃ and 107Kg/cm 2 ,
Changes in the surface condition of the test piece, weight changes due to corrosion of the test piece (corrosion amount), changes in hydrogen content in the test piece, and internal structure of the test piece were observed. According to this test, the surface condition after 40 hours of holding time was as shown in Figure 1b, with no white products observed at all, and the amount of corrosion was excellent, with almost no increase as shown by curve b in Figure 2. It has excellent nodular corrosion resistance. On the other hand, as mentioned above, the hydrogen content, which is related to nodular corrosion properties, is also the third factor.
As shown by curve b in the figure, almost no increase was observed, and even in the internal structure, hydride ZrHx
The amount of black material attributed to the material was also extremely small.
上記具体例から明らかのように本発明に係る表
面近傍に酸素拡散層を有するジルコニウム合金は
すぐれた耐ノジユラーコロージヨン性を備えてい
る。かくして本発明に係る耐ノジユラーコロージ
ヨン性ジルコニウム合金は例えばチヤンネルボツ
クスや燃料被覆管など炉心構造物の素材として用
いた場合も長期間に亘つて構造材として所要の機
能を果し得ると言える。 As is clear from the above examples, the zirconium alloy according to the present invention having an oxygen diffusion layer near its surface has excellent nodular corrosion resistance. Thus, it can be said that the nodular corrosion-resistant zirconium alloy according to the present invention can perform the required functions as a structural material for a long period of time even when used as a material for reactor core structures such as channel boxes and fuel cladding tubes.
尚上記においてはジルコニウム基合金について
Zr―Sn―Fe系について示したがその他Zr―2.5％
Nb系やZr―１％Nb系、或いはオーゼナイトなど
のジルコニウム基合金についても同様であり、ま
た酸素拡散層の形成は例えばオートクレーブ処理
を可成り長時間施すことなどによつても達成でき
る。 The above description refers to zirconium-based alloys.
Shown is for Zr-Sn-Fe system, but other Zr-2.5%
The same applies to Nb-based alloys, Zr-1%Nb-based alloys, or zirconium-based alloys such as Auzenite. Formation of an oxygen diffusion layer can also be achieved, for example, by performing autoclave treatment for a fairly long time.
添附図は本発明に係るジルコニウム合金および
本発明外のジルコニウム合金について耐ノジユラ
ーコロージヨン性の加速試験結果を比較して示す
もので第１図ａ，ｂは表面状態を示す写真、第２
図ａ，ｂは腐食による重量変化の状態を示す曲線
図、第３図ａ，ｂは合金内部の水素含量の変化を
示す曲線図、第４図ａ，ｂは内部組織の状態を示
す顕微鏡写真である。
The attached figures compare and show the results of accelerated nodular corrosion resistance tests for zirconium alloys according to the present invention and zirconium alloys other than the present invention.
Figures a and b are curve diagrams showing the state of weight change due to corrosion, Figure 3 a and b are curve diagrams showing the change in hydrogen content inside the alloy, and Figure 4 a and b are micrographs showing the state of the internal structure. It is.
Claims (1)
の拡散層を形成して成ることを特徴とする耐ノジ
ユラーコロージヨン性ジルコニウム合金。 ２ 特許請求の範囲第１項において、ジルコニウ
ム基合金が、重量比で錫１〜1.8％、鉄0.1〜0.2
％、ニツケル0.1％以下、クロム0.2％以下および
残部ジルコニウムから成ることを特徴とする耐ノ
ジユラーコロージヨン性ジルコニウム合金。 ３ ジルコニウム基合金を、１×10-3mmHg〜１
×104mmHgの酸素雰囲気中、500〜1000℃の温度
下に放置し、前記ジルコニウム基合金の表面近傍
に酸素の拡散層を形成することを特徴とする耐ノ
ジユラーコロージヨン性ジルコニウム合金の製造
方法。 ４ 特許請求の範囲第３項において、ジルコニウ
ム基合金が、重量比で錫１〜1.8％、鉄0.1〜0.2
％、ニツケル0.1％以下、クロム0.2％以下および
残部ジルコニウムからなることを特徴とする耐ノ
ジユラーコロージヨン性ジルコニウム合金の製造
方法。[Scope of Claims] 1. A nodular corrosion-resistant zirconium alloy characterized by forming an oxygen diffusion layer near the surface of a zirconium-based alloy substrate. 2. In claim 1, the zirconium-based alloy contains 1 to 1.8% tin and 0.1 to 0.2% iron by weight.
%, 0.1% or less of nickel, 0.2% or less of chromium, and the balance zirconium. 3 Zirconium-based alloy, 1×10 -3 mmHg ~ 1
Production of a nodular corrosion-resistant zirconium alloy characterized by forming an oxygen diffusion layer near the surface of the zirconium-based alloy by leaving it at a temperature of 500 to 1000°C in an oxygen atmosphere of ×10 4 mmHg. Method. 4 In claim 3, the zirconium-based alloy contains 1 to 1.8% tin and 0.1 to 0.2% iron by weight.
%, 0.1% or less of nickel, 0.2% or less of chromium, and the remainder zirconium.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP12232180A JPS5747867A (en) | 1980-09-05 | 1980-09-05 | Zirconium alloy with nodular corrosion resistance and its manufacture |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP12232180A JPS5747867A (en) | 1980-09-05 | 1980-09-05 | Zirconium alloy with nodular corrosion resistance and its manufacture |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5747867A JPS5747867A (en) | 1982-03-18 |
| JPS6115950B2 true JPS6115950B2 (en) | 1986-04-26 |
Family
ID=14833065
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP12232180A Granted JPS5747867A (en) | 1980-09-05 | 1980-09-05 | Zirconium alloy with nodular corrosion resistance and its manufacture |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5747867A (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2674052B2 (en) * | 1988-01-22 | 1997-11-05 | 三菱マテリアル株式会社 | Zr alloy with excellent corrosion resistance for reactor fuel cladding |
| JPS6335749A (en) * | 1986-07-29 | 1988-02-16 | Mitsubishi Metal Corp | Zr alloy for nuclear reactor fuel clad pipe excellent in corrosion resistance |
-
1980
- 1980-09-05 JP JP12232180A patent/JPS5747867A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5747867A (en) | 1982-03-18 |
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