JPS63179034A - Corrosion-resisting zirconium alloy - Google Patents
Corrosion-resisting zirconium alloyInfo
- Publication number
- JPS63179034A JPS63179034A JP62011597A JP1159787A JPS63179034A JP S63179034 A JPS63179034 A JP S63179034A JP 62011597 A JP62011597 A JP 62011597A JP 1159787 A JP1159787 A JP 1159787A JP S63179034 A JPS63179034 A JP S63179034A
- Authority
- JP
- Japan
- Prior art keywords
- corrosion
- content
- zircaloy
- zirconium alloy
- nodular
- 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
- 229910001093 Zr alloy Inorganic materials 0.000 title claims abstract description 25
- 238000005260 corrosion Methods 0.000 claims abstract description 66
- 230000007797 corrosion Effects 0.000 claims abstract description 66
- 229910052742 iron Inorganic materials 0.000 claims abstract description 5
- 229910052726 zirconium Inorganic materials 0.000 claims description 2
- 229910052804 chromium Inorganic materials 0.000 abstract description 5
- 229910052759 nickel Inorganic materials 0.000 abstract description 4
- 238000004519 manufacturing process Methods 0.000 abstract description 3
- 239000000203 mixture Substances 0.000 abstract description 3
- 229910045601 alloy Inorganic materials 0.000 abstract description 2
- 239000000956 alloy Substances 0.000 abstract description 2
- 229910052718 tin Inorganic materials 0.000 abstract description 2
- 239000000446 fuel Substances 0.000 description 5
- 238000005253 cladding Methods 0.000 description 4
- 230000007423 decrease Effects 0.000 description 4
- 239000000047 product Substances 0.000 description 4
- 238000009835 boiling Methods 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- 239000000463 material Substances 0.000 description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 3
- 229910001257 Nb alloy Inorganic materials 0.000 description 2
- 238000000137 annealing Methods 0.000 description 2
- 229910000765 intermetallic Inorganic materials 0.000 description 2
- 241000519995 Stachys sylvatica Species 0.000 description 1
- 229910052770 Uranium Inorganic materials 0.000 description 1
- 238000010521 absorption reaction Methods 0.000 description 1
- 230000015572 biosynthetic process Effects 0.000 description 1
- 238000005097 cold rolling Methods 0.000 description 1
- 238000004042 decolorization Methods 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 230000003111 delayed effect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000005242 forging Methods 0.000 description 1
- 150000004678 hydrides Chemical class 0.000 description 1
- 229910052739 hydrogen Inorganic materials 0.000 description 1
- 239000001257 hydrogen Substances 0.000 description 1
- 125000004435 hydrogen atom Chemical class [H]* 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 239000002244 precipitate Substances 0.000 description 1
- 238000010791 quenching Methods 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 239000002901 radioactive waste Substances 0.000 description 1
- 230000007704 transition Effects 0.000 description 1
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 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
Abstract
Description
【発明の詳細な説明】
［産業上の利用分野］
本発明は耐蝕性ジルコニウム合金に関し、さらに詳しく
は、耐ノジユラー腐蝕性に優れ、かつ、耐均−腐蝕性に
優れた耐蝕性ジルコニウム合金に関する。DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to a corrosion-resistant zirconium alloy, and more particularly to a corrosion-resistant zirconium alloy that has excellent nodular corrosion resistance and excellent uniform corrosion resistance.
［従来技術］
一般的に、ジルコニウム合金は小さい中性子吸収断面積
および優れた耐蝕性を有していることから、沸騰水型軽
水炉の構造材料である燃料被覆管として広く使用されて
いる。[Prior Art] In general, zirconium alloys have a small neutron absorption cross section and excellent corrosion resistance, and are therefore widely used as fuel cladding tubes, which are structural materials for boiling water reactors.
そして、これまでに最も普通に使用されているジルコニ
ウム合金としては、ＡＳＴＭに規定されているノルカロ
イ−２、ジルカロイ−４があり、その他、Ｎｂ １ｗｔ
％含有のＺｒ−１ｖｔ％Ｎｂ合金、Ｎｂ ２．５ｗｔ％
含有のＺｒ−２，５ｗ１％Ｎｂ合金、ＮｂＯ，１ｗｔ％
、Ｎｉ ０．１ｗｔ％、Ｆｅ Ｏ，ｔｖｔ％、Ｓｎ ｏ
、２ｗｔ％含有の０ｚｈｅｎｉｔｅおよびＰｅ ０．１
ｗｔ％以下、Ｃｒ１．０ｗｔ％以下含有するＶａｌｏｙ
がある。The most commonly used zirconium alloys to date include Norcaloy-2 and Zircaloy-4 specified by ASTM, as well as Nb 1wt.
% containing Zr-1vt%Nb alloy, Nb 2.5wt%
Contains Zr-2,5w1%Nb alloy, NbO,1wt%
, Ni 0.1 wt%, Fe O, tvt%, Sn o
, 2wt% of 0zhenite and Pe 0.1
Valoy containing Cr1.0wt% or less
There is.
しかし、これらの合金の耐蝕性は必ずしも充分なものと
はいえず、例えば、沸騰水型軽水炉のチャネルボックス
にジルカロイ−４を、燃料被覆管にジルカロイ−２を使
用すると、ノジュラー腐蝕と呼ばれる白色斑点状の腐蝕
が発生することがある。However, the corrosion resistance of these alloys is not necessarily sufficient. For example, when Zircaloy-4 is used in the channel box of a boiling water reactor and Zircaloy-2 is used in the fuel cladding tube, white spots called nodular corrosion occur. Corrosion may occur.
そして、このノジュラー腐蝕が進展すると、時には剥離
現象を起こして肉減りし、構造材料として機械的性質の
低下をもたらす恐れがあり、また、剥離した腐蝕生成物
は放射能を有し取り扱い上好ましくない。そのため、原
子炉の構造材料としてのジルコニウム合金の耐ノジユラ
ー腐蝕特性を改善することが注目されるようになってき
た。As this nodular corrosion progresses, it sometimes causes a peeling phenomenon and thinning, which may lead to a decrease in the mechanical properties of the structural material.Furthermore, the peeled corrosion products are radioactive and undesirable for handling. . Therefore, attention has been focused on improving the nodular corrosion resistance of zirconium alloys as structural materials for nuclear reactors.
さらに、ウラン資源の有効利用、放射性廃棄物の発生量
の低減および発電コストの低減を目的として燃料の高燃
焼度化が進められている。そのため、上記ジルカロイ製
品等炉内構造物にはノジュラー腐蝕のような局部腐蝕に
対する耐蝕性ばかりでなく、均一腐蝕に対する耐蝕性に
優れていることが望まれている。Furthermore, efforts are being made to increase the burnup of fuel with the aim of effectively utilizing uranium resources, reducing the amount of radioactive waste generated, and reducing power generation costs. Therefore, it is desired that the above-mentioned Zircaloy products and other furnace internal structures have excellent corrosion resistance not only against localized corrosion such as nodular corrosion, but also against uniform corrosion.
［発明か解決しようとする問題点］
本発明は上記に説明した従来におけるジルコニウム合金
のノジュラー腐蝕に鑑み、本発明者は脱色研究を行い、
検討を重ねた結果、通常の耐蝕性ジルコニウム合金の製
造工程、即ち、溶解−鍛造→β焼入れ（約１０００℃の
温度に２０分保持後水冷、マメテンサイド組織）−熱間
加工（８００℃）−冷間圧延→焼鈍（７００℃、等軸品
）→製品の工程で作られたジルコニウム合金、例えば、
ジルカロイ−２、ジルカロイ−４と比較して、Ｆｅ、Ｃ
ｒおよびＮｉ含有量はジルカロイ−２またはジルカロイ
−４の含有量と同等であるがＳｎ含有量を低く制御する
ことにより、ノジュラー腐蝕の発生が極めて少量となる
こと、あるいは、均一腐蝕に対する腐蝕速度も極めて小
さくなり、酸化膜の剥離開始が遅くなり、また、最終焼
鈍条件によっても変化しないことを見出だし、ジルコニ
ウム合金、例えば、ジルカロイ−２およびジルカロイ−
４で作られたチャネルボックスや燃料被覆管に発生する
ノジュラー腐蝕の発生を防止し、並びに均一腐蝕を極力
抑えることができる耐蝕性ジルコニウム合金を開発した
のである。[Problems to be solved by the invention] In view of the nodular corrosion of conventional zirconium alloys explained above, the present inventor conducted decolorization research,
As a result of repeated studies, we decided to follow the usual manufacturing process for corrosion-resistant zirconium alloys: Melting - Forging -> β-quenching (held at a temperature of about 1000°C for 20 minutes, then water-cooled, mameten side structure) - Hot working (800°C) - Cold rolling → annealing (700℃, equiaxed product) → Zirconium alloy made in the process of product, e.g.
Compared to Zircaloy-2 and Zircaloy-4, Fe, C
The r and Ni contents are equivalent to the Zircaloy-2 or Zircaloy-4 contents, but by controlling the Sn content low, the occurrence of nodular corrosion will be extremely small, or the corrosion rate will be lower than that of uniform corrosion. They found that the size of the oxide film becomes extremely small, the start of peeling of the oxide film is delayed, and that it does not change depending on the final annealing conditions.
We have developed a corrosion-resistant zirconium alloy that can prevent the occurrence of nodular corrosion that occurs in channel boxes and fuel cladding tubes made with 4, as well as suppress uniform corrosion as much as possible.
［問題点を解決するための手段］
本発明に係る耐蝕性ジルコニウム合金は、Ｓｎ １．Ｏ
ｖｔ％以下、Ｆｅ Ｏ，０５〜０．５ｖｔ％、Ｃｒ ０
．３ｗｔ％以下、
Ｎｉ Ｏ，２ｗｔ％以下
を含有し、残部実質的にＺｒからなることを特徴とする
耐蝕性ジルコニウム合金である。[Means for Solving the Problems] The corrosion-resistant zirconium alloy according to the present invention contains Sn1. O
vt% or less, Fe O, 05 to 0.5 vt%, Cr 0
．． This is a corrosion-resistant zirconium alloy characterized by containing 3wt% or less of NiO, 2wt% or less of NiO, and the remainder substantially consisting of Zr.
以下本発明に係る耐蝕性ジルコニウム合金について以下
詳細に説明する。The corrosion-resistant zirconium alloy according to the present invention will be explained in detail below.
先ず、本発明に係る原子炉用ジルコニウム合金の含有成
分および含有割合について説明する。First, the components and content ratios of the zirconium alloy for nuclear reactors according to the present invention will be explained.
本発明者の研究によれば、Ｓ ｎ １．２０〜１．７０
ｗＬ％、Ｆｅ Ｏ，０７〜０．２４ｖｔ％、Ｃｒ ０．
０５〜０．１５ｗｔ％を含有し、また、Ｎｉ ０．０８
ｖｔ％を含有し、または、含有しないジルカロイ−２お
よびジルカロイ−４の耐蝕性は、含有成分であるＳｎ、
Ｆｅ、ＣｒおよびＮｉの含有量によりいつじるしく影響
を受け、ＦｅおよびＮ１は耐蝕性改善効果を有し、Ｓｎ
は逆に耐蝕性をやや劣化させ、Ｃｒは耐蝕性にはあまり
寄与しないこと、また、ジルコニウムにＦｅまたはＮｉ
を含有させると均一腐蝕がジルカロイ−２およびジルカ
ロイ−４より小さくなり、ノジュラー腐蝕に耐えること
がわかった。According to the research of the present inventor, S n 1.20 to 1.70
wL%, FeO, 07-0.24vt%, Cr 0.
05 to 0.15 wt%, and Ni 0.08
The corrosion resistance of Zircaloy-2 and Zircaloy-4 with or without vt% is determined by the contained components Sn,
It is severely affected by the content of Fe, Cr and Ni, with Fe and N1 having the effect of improving corrosion resistance, and Sn
On the contrary, Cr slightly deteriorates corrosion resistance, and Cr does not contribute much to corrosion resistance.
It was found that the uniform corrosion was smaller than that of Zircaloy-2 and Zircaloy-4 when Zircaloy-4 was added, and that it was resistant to nodular corrosion.
先ず、本発明に係る耐蝕性ジルコニウム合金の含有成分
および含有割合について説明する。First, the components and content ratios of the corrosion-resistant zirconium alloy according to the present invention will be explained.
Ｓｎ含有量が増加するとノジュラー腐蝕を発生させ、均
一腐蝕速度を増加し、そして、腐蝕増量の関係から含有
量が１．１ｗｔ％を越えて含有されるとノジュールの発
生が認められるが、含ＴＴｍが１．０ｗ１％未満ではノ
ジールの発生は認められず、均一腐蝕速度もＳｎ含有量
が多い場合に比べてかなり低くなる。よって、Ｓｎ含有
量は＋、Ｏｗｔ％以下とする。When the Sn content increases, nodular corrosion occurs and the uniform corrosion rate increases.If the Sn content exceeds 1.1 wt%, the formation of nodules is observed due to the increase in corrosion. When the Sn content is less than 1.0w1%, no nozzle generation is observed, and the uniform corrosion rate is considerably lower than when the Sn content is high. Therefore, the Sn content is set to below +, Owt%.
Ｆｅは耐ノジユラー腐蝕性を付与する元素であり、含有
ｍが０．０５ｗｔ％未満では耐ツノニラ−腐蝕性が劣り
、また、ｏ 、 ５ｖｔ％を越えて含有されるとＺｒと
の金属間化合物が増加して加工が困難となる。よって、
Ｆｅ含有量は０．０５〜０．５ｗｔ％とする。Fe is an element that imparts nodular corrosion resistance, and if the content m is less than 0.05wt%, the nodular corrosion resistance is poor, and if the content exceeds 5wt%, an intermetallic compound with Zr is formed. increases, making processing difficult. Therefore,
The Fe content is 0.05 to 0.5 wt%.
Ｎ１は耐ノジユラー腐蝕性を改善する元素であり、含有
量が０．２ｗｔ％を越えて含有されると水素を吸収し易
くなり、水素化物を析出して機械的性質を低下させる。N1 is an element that improves nodular corrosion resistance, and when the content exceeds 0.2 wt%, it tends to absorb hydrogen, precipitates hydrides, and deteriorates mechanical properties.
よって、Ｎｉ含有量は０．２ｗｔ％以下とする。Therefore, the Ni content is set to 0.2 wt% or less.
Ｃｒは耐ノジユラー腐蝕性を改善する元素であり、含有
量が０．３ｗｔ％を越えて含有されるとＺｒとの金属間
化合物を増加して、加工が困難となる。Cr is an element that improves nodular corrosion resistance, and if the content exceeds 0.3 wt%, it increases intermetallic compounds with Zr, making processing difficult.
よって、Ｃｒ含有量は０．３ｗｔ％以下とする。Therefore, the Cr content is set to 0.3 wt% or less.
［実 施 例コ
本発明に係る耐蝕性ジルコニウム合金の実施例を説明す
る。[Example] An example of the corrosion-resistant zirconium alloy according to the present invention will be described.
実施例
本発明に係る耐蝕性ジルコニウム合金において、Ｓｎ含
有量の変化による腐蝕増量について５００℃×２４時間
のオートクレーブ腐蝕試験を行った。EXAMPLE An autoclave corrosion test at 500° C. for 24 hours was conducted on the corrosion-resistant zirconium alloy according to the present invention to examine the increase in corrosion due to changes in Sn content.
その結果、耐蝕性の変化を第１図により具体的に説明す
る。As a result, changes in corrosion resistance will be explained in detail with reference to FIG.
第１図は、ジルカロイ−２（第１図でＯで示す。FIG. 1 shows Zircaloy-2 (indicated by O in FIG. 1).
）またはジルカロイ−４（第１図で・で示す。）に含有
さ仕るＳｎ含有量を変化させた場合の腐蝕増量（試験条
件は５００°Ｃ×２４時間）を示しているが、Ｓｎ含有
量の減少と共に腐蝕増量が減少しているのがわかる。特
に、ジルカロイ−４の場合、Ｓｎ含有量を減少させると
腐蝕増量は急激に減少し、成分規格の下限含有量近＜
（Ｓ ｎ １．２５ｗｔ％）の試料にはノジールの発生
が認められたが、Ｓｎ含有量が１．Ｏｖｔ％以下の試料
にはノジールは全く発生していなかった。なお、第１図
において、ＡはＡＳＴＭ規格を示す。) or Zircaloy-4 (indicated by . in Figure 1). It can be seen that the corrosion increase decreases as the amount decreases. In particular, in the case of Zircaloy-4, when the Sn content is decreased, the corrosion increase rapidly decreases, and the content is close to the lower limit of the component specification.
(S n 1.25 wt %) sample showed nozzle generation, but the Sn content was 1.25 wt %. No nozzle was generated in the samples with Ovt% or less. Note that in FIG. 1, A indicates the ASTM standard.
第２図（ａＸｂ）は試験時間を延長した場合の腐蝕増量
（試験条件は４００℃ｘ Ｉ ０５ ｋｇ／ｃ＋ｎ”）
の変化を示したものである。Figure 2 (aXb) shows the increase in corrosion when the test time is extended (test conditions are 400℃ x I 05 kg/c+n”)
This shows the changes in
第２図（ａ）はＳｎ含有量を変化させたジルカロイ−４
について、また、第２図（ｂ）はＳｎ含有量を変化させ
たジルカロイ−２についての測定値を示したしのである
。なお、第２図（ａ）において、・はＳｎ含有ｊｌ ２
．１１ｖｔ％、○はＳｎ含有量１．４５ｗｔ％、ＯはＳ
ｎ含有量１．００ｗｔ％を示し、また、第２図（ｂ）に
おいて、・はＳｎ含有＠ ２．２０ｖｔ％、○はＳｎ含
有ｆｆｉ １．４５ｗｔ％、ＯはＳｎ含有量１．００ｗ
ｔ％をそれぞれ示している。Figure 2(a) shows Zircaloy-4 with varying Sn content.
Also, FIG. 2(b) shows measured values for Zircaloy-2 with varying Sn content. In addition, in FIG. 2(a), . represents Sn-containing jl 2
．． 11vt%, ○ means Sn content 1.45wt%, O means S
Indicates n content of 1.00wt%, and in Fig. 2(b), * indicates Sn content @ 2.20vt%, ○ indicates Sn content ffi 1.45wt%, and O indicates Sn content of 1.00w.
t% is shown respectively.
標準組成のジルカロイ−４またはジルカロイ−２と比較
して、Ｓｎ含有量を減少させたジルカロイは腐蝕増量が
少ないばかりでなく、腐蝕増量が急増する遷移（第２図
中腐蝕増量を結ぶ直線が折れる点で示される。）後の均
一腐蝕速度（直線の傾きで示される。）が小さく、均一
腐蝕特性に優れていることがわかる。Compared to Zircaloy-4 or Zircaloy-2 of standard composition, Zircaloy with reduced Sn content not only exhibits less corrosion increase, but also shows a transition where the corrosion increase rapidly occurs (in Figure 2, the straight line connecting the corrosion increase is broken). It can be seen that the uniform corrosion rate (indicated by the slope of the straight line) after (indicated by a dot) is small, and the uniform corrosion characteristics are excellent.
従って、Ｓｎの含有量は１．０ｗｔ％以下とするのがよ
い。Therefore, the content of Sn is preferably 1.0 wt% or less.
［発明の効果］
以上説明したように、本発明に係る耐蝕性ジルコニウム
合金は上記の構成であるから、例えば、沸騰水型軽水炉
で使用されるチャネル、燃料被覆管を製造してもノジュ
ラー腐蝕の発生は極めて少なく安全に操業することがで
き、さらに、長期間原子炉ないで使用されても、均一腐
蝕の進行が抑制されるために長期間健全性を保持できる
という優れた効果を奏するものである。[Effects of the Invention] As explained above, since the corrosion-resistant zirconium alloy according to the present invention has the above structure, nodular corrosion can be avoided even when manufacturing channels and fuel cladding tubes used in boiling water reactors, for example. It can be operated safely with very little occurrence, and even if it is used without a nuclear reactor for a long time, it has the excellent effect of maintaining its integrity for a long period of time because the progress of uniform corrosion is suppressed. be.
第１図はジルカロイ−２またはジルカロイ−４に含有さ
れるＳｎ含有量の変化と腐蝕増量との関係を示す図、第
２図はＳｎ含有量を変化させたジルカロイ−２およびジ
ルカロイ−４の試験時間と腐蝕増量の関係を示す図であ
る。
矛１ 図
０ １．２ ２．０、Ｓｎ
宕鳴ｉ （ｗｔｚ）
刃占 令室 かカ１ ど−シ２ン一・）腐 蝕槽ｉ（
−角−＝）Figure 1 is a diagram showing the relationship between changes in Sn content contained in Zircaloy-2 or Zircaloy-4 and corrosion increase, and Figure 2 is a test of Zircaloy-2 and Zircaloy-4 with varying Sn contents. It is a figure showing the relationship between time and corrosion increase. Spear 1 Figure 0 1.2 2.0, Sn
Minaki i (wtz) blade fortune telling room ka 1 do-shi 2 in 1・) corrosive tank i (
-Angle-=)
Claims (1)
Ｃｒ０．３ｗｔ％以下、 Ｎｉ０．２ｗｔ％以下 を含有し、残部実質的にＺｒからなることを特徴とする
耐蝕性ジルコニウム合金。[Claims] Sn 1.0 wt% or less, Fe 0.05 to 0.5 wt%,
A corrosion-resistant zirconium alloy containing 0.3 wt% or less of Cr, 0.2 wt% or less of Ni, and the remainder substantially consisting of Zr.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62011597A JP2675297B2 (en) | 1987-01-21 | 1987-01-21 | Corrosion resistant zirconium alloy |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62011597A JP2675297B2 (en) | 1987-01-21 | 1987-01-21 | Corrosion resistant zirconium alloy |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS63179034A true JPS63179034A (en) | 1988-07-23 |
| JP2675297B2 JP2675297B2 (en) | 1997-11-12 |
Family
ID=11782313
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP62011597A Expired - Lifetime JP2675297B2 (en) | 1987-01-21 | 1987-01-21 | Corrosion resistant zirconium alloy |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2675297B2 (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH02173235A (en) * | 1988-12-27 | 1990-07-04 | Toshiba Corp | Corrosion resisting zirconium alloy |
| CN115747570A (en) * | 2022-10-31 | 2023-03-07 | 上海大学 | Zirconium alloy cladding material for small pressurized water reactor and preparation method thereof |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS57134552A (en) * | 1981-02-13 | 1982-08-19 | Toshiba Corp | Zirconium alloy substrate |
| JPS58224139A (en) * | 1982-06-21 | 1983-12-26 | Hitachi Ltd | Zirconium alloy with high corrosion resistance |
| JPS6299432A (en) * | 1985-10-22 | 1987-05-08 | ウエスチングハウス エレクトリック コ−ポレ−ション | Fuel coated pipe comprising single zirconium base alloy |
| JPS63145735A (en) * | 1986-12-08 | 1988-06-17 | Sumitomo Metal Ind Ltd | Zirconium alloy |
-
1987
- 1987-01-21 JP JP62011597A patent/JP2675297B2/en not_active Expired - Lifetime
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS57134552A (en) * | 1981-02-13 | 1982-08-19 | Toshiba Corp | Zirconium alloy substrate |
| JPS58224139A (en) * | 1982-06-21 | 1983-12-26 | Hitachi Ltd | Zirconium alloy with high corrosion resistance |
| JPS6299432A (en) * | 1985-10-22 | 1987-05-08 | ウエスチングハウス エレクトリック コ−ポレ−ション | Fuel coated pipe comprising single zirconium base alloy |
| JPS63145735A (en) * | 1986-12-08 | 1988-06-17 | Sumitomo Metal Ind Ltd | Zirconium alloy |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH02173235A (en) * | 1988-12-27 | 1990-07-04 | Toshiba Corp | Corrosion resisting zirconium alloy |
| CN115747570A (en) * | 2022-10-31 | 2023-03-07 | 上海大学 | Zirconium alloy cladding material for small pressurized water reactor and preparation method thereof |
Also Published As
| Publication number | Publication date |
|---|---|
| JP2675297B2 (en) | 1997-11-12 |
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