JPH10219376A - Soft zirconium alloy excellent in hydrogen absorbing characteristic and stress corrosion cracking resistance in high temperature-high pressure water vapor atmosphere - Google Patents
Soft zirconium alloy excellent in hydrogen absorbing characteristic and stress corrosion cracking resistance in high temperature-high pressure water vapor atmosphereInfo
- Publication number
- JPH10219376A JPH10219376A JP9039702A JP3970297A JPH10219376A JP H10219376 A JPH10219376 A JP H10219376A JP 9039702 A JP9039702 A JP 9039702A JP 3970297 A JP3970297 A JP 3970297A JP H10219376 A JPH10219376 A JP H10219376A
- Authority
- JP
- Japan
- Prior art keywords
- soft
- stress corrosion
- corrosion cracking
- cracking resistance
- hydrogen absorbing
- 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.)
- Pending
Links
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
- Preventing Corrosion Or Incrustation Of Metals (AREA)
Abstract
Description
【０００１】[0001]
【発明の属する技術分野】本発明は、原子炉材料に用い
られるジルコニウム合金に関するものである。TECHNICAL FIELD The present invention relates to a zirconium alloy used for a reactor material.
【０００２】[0002]
【従来の技術】一般に、純ジルコニウムは急激な酸化に
対する抑制力を持つが、原子炉材料として用いるには耐
食性が低いため、Ｆｅ、Ｃｒ、Ｎｉ、Ｓｎ、Ｎｂ等の種
々の合金元素を添加したジルコニウム合金（ジルカロ
イ）が用いられている。このジルカロイは、純ジルコニ
ウムに比べて高温高圧水蒸気中での耐食性が良く、原子
炉材料に適したものである。2. Description of the Related Art In general, pure zirconium has a suppressive power against rapid oxidation, but since it has low corrosion resistance when used as a reactor material, various alloying elements such as Fe, Cr, Ni, Sn and Nb are added. A zirconium alloy (Zircaloy) is used. This zircaloy has better corrosion resistance in high-temperature and high-pressure steam than pure zirconium, and is suitable for a reactor material.
【０００３】ジルカロイには、添加する合金元素の種類
や量に応じてジルカロイ２やジルカロイ４等の種類があ
り、燃焼条件や原子炉の型、即ち、沸騰水型か加圧水型
かなどの違いにより、最も適した種類のジルカロイが選
択され使用されている。[0003] Zircaloys include Zircaloy 2 and Zircaloy 4 depending on the type and amount of alloying elements to be added. Depending on the combustion conditions and the type of reactor, that is, the boiling water type or pressurized water type, etc. The most suitable type of Zircaloy is selected and used.
【０００４】[0004]
【発明が解決しようとする課題】しかしながら、純ジル
コニウムに比べて従来のジルカロイは、高温高圧水蒸気
中での耐食性が良い反面、合金元素添加のために機械的
強度が強くなってしまう。そのため、成形加工性性が悪
くなってしまい、軟質な性質が必要とされる用途には利
用できないという難点がある。However, as compared with pure zirconium, conventional zircaloy has good corrosion resistance in high-temperature and high-pressure steam, but has high mechanical strength due to the addition of alloying elements. Therefore, there is a disadvantage that the moldability is deteriorated, and it cannot be used for applications requiring soft properties.
【０００５】また、ＣｒやＮｉを添加して得たジルカロ
イは、水素を吸収し易くなるため好ましくなく、Ｎｂの
みを添加して得たジルカロイは、水素吸収特性は改善さ
れるものの機械的強度が強くなることは避けられないと
いう欠点がある。[0005] Zircaloy obtained by adding Cr or Ni is not preferred because it easily absorbs hydrogen. Zircaloy obtained by adding only Nb has improved hydrogen absorption characteristics, but has poor mechanical strength. There is a disadvantage that it becomes unavoidable to become strong.
【０００６】加えて、ジルカロイは、炉内の核分裂反応
で生じるヨウ素に対する応力腐食割れ感受性が高くな
り、相対的に応力腐食割れに対する耐性が低下するとい
う欠点も持っている。[0006] In addition, Zircaloy has a disadvantage that stress corrosion cracking susceptibility to iodine generated by a nuclear fission reaction in a furnace is increased, and resistance to stress corrosion cracking is relatively reduced.
【０００７】本発明は、急激な酸化に対する抑制力を維
持しつつ、純ジルコニウムと同等の軟質な機械的特性を
有し、且つ高温高圧水蒸気雰囲気中での水素吸収特性お
よび耐応力腐食割れ性を向上させた軟質ジルコニウム合
金を提供するものである。The present invention has the same soft mechanical properties as pure zirconium while maintaining the ability to suppress rapid oxidation, and exhibits hydrogen absorption characteristics and stress corrosion cracking resistance in a high-temperature, high-pressure steam atmosphere. An object of the present invention is to provide an improved soft zirconium alloy.
【０００８】[0008]
【課題を解決するための手段】上記目的を達成すべく、
請求項１の発明は、ジルコニウム中に微量添加物とし
て、０．１ｗｔ％以上０．６ｗｔ％以下のＦｅを含み、
酸素の含有量が1200ppm以下、その他不可避不純物の含
有量が2000ppm 以下であることを特徴とする高温高圧水
蒸気雰囲気中での水素吸収特性及び耐応力腐食割れ性に
優れた軟質ジルコニウム合金としている。In order to achieve the above object,
The invention according to claim 1 includes zirconium containing 0.1 wt% or more and 0.6 wt% or less of Fe as a trace additive,
A soft zirconium alloy excellent in hydrogen absorption characteristics and stress corrosion cracking resistance in a high-temperature, high-pressure steam atmosphere characterized by having an oxygen content of 1200 ppm or less and other unavoidable impurities of 2000 ppm or less.
【０００９】即ち、酸素含有量が1200ppm 以下で、その
他不可避不純物を2000ppm 以下にしたジルコニウムを用
い、このジルコニウムに含まれる合金元素をＦｅに限定
すると共に、その量を限定することで、急激な酸化に対
する抑制力を維持しつつ、純ジルコニウムと同等の軟質
な機械的特性を有し、且つ高温高圧水蒸気雰囲気中での
水素吸収特性および耐応力腐食割れ性を向上させた軟質
ジルコニウム合金としている。That is, zirconium having an oxygen content of 1200 ppm or less and other unavoidable impurities of 2000 ppm or less is used, and the alloying element contained in the zirconium is limited to Fe, and by limiting the amount thereof, rapid oxidation is performed. A soft zirconium alloy having soft mechanical properties equivalent to that of pure zirconium while maintaining the suppressing force against hydrogen, and having improved hydrogen absorption properties and stress corrosion cracking resistance in a high-temperature, high-pressure steam atmosphere.
【００１０】この様な範囲内とすることで、水素吸収特
性がジルカロイ２及び純ジルコニウムよりも向上したも
のとなるだけでなく、純ジルコニウム相当の硬さを持つ
ものから、ジルカロイ２相当の硬さを持つものまで得ら
れるので用途に応じて適当な硬度のものを選択すること
ができる。By setting the content within such a range, not only is the hydrogen absorption property improved than that of zircaloy 2 and pure zirconium, but also the hardness from pure zirconium to hardness equivalent to zircaloy 2 is obtained. Can be selected, so that a material having an appropriate hardness can be selected according to the application.
【００１１】また、耐食性の微小な調整を行うためにＮ
ｉ等の他の合金元素を添加してもよく、この場合、あま
り多量に添加すると水素吸収特性が悪化するためその兼
ね合いを考慮して添加量を決定すると良い。In order to finely adjust the corrosion resistance, N
Other alloying elements such as i may be added. In this case, if added in a large amount, the hydrogen absorption characteristics are deteriorated. Therefore, it is preferable to determine the amount to be added in consideration of the balance.
【００１２】尚、ジルコニウム中に含まれるＦｅの量を
０．１ｗｔ％以上０．６ｗｔ％以下としたのは、Ｆｅ量
が０．１ｗｔ％より少ないと耐食性が十分に改良され
ず、逆に０．６ｗｔ％を超えると機械的強度がジルカロ
イ２よりも強くなってしまい加工性の面で好ましくない
だけでなく、高温高圧水蒸気雰囲気中での水素吸収特性
および耐応力腐食割れ性が悪化するからである。The reason why the amount of Fe contained in zirconium is set to 0.1 wt% or more and 0.6 wt% or less is that if the Fe content is less than 0.1 wt%, the corrosion resistance is not sufficiently improved, and conversely, 0 wt%. If it exceeds 0.6 wt%, the mechanical strength becomes stronger than that of Zircaloy 2, which is not preferable in terms of workability, and also deteriorates the hydrogen absorption characteristics and the stress corrosion cracking resistance in a high-temperature and high-pressure steam atmosphere. is there.
【００１３】また、請求項２の発明は、請求項１に記載
の高温高圧水蒸気雰囲気中での水素吸収特性及び耐応力
腐食割れ性に優れた軟質ジルコニウム合金において、Ｆ
ｅの含有量が０．１ｗｔ％以上０．４ｗｔ％以下である
ものとしている。According to a second aspect of the present invention, there is provided a soft zirconium alloy according to the first aspect, which is excellent in hydrogen absorption characteristics and stress corrosion cracking resistance in a high-temperature and high-pressure steam atmosphere.
The content of e is not less than 0.1 wt% and not more than 0.4 wt%.
【００１４】前記軟質ジルコニウム合金におけるＦｅ量
が０．１ｗｔ％より少ないと耐食性が十分に改良され
ず、０．４ｗｔ％を超えると機械的強度が純ジルコニウ
ムよりも大きくなる。そのため、請求項２の発明では、
前記軟質ジルコニウム合金が含むＦｅ量を０．１ｗｔ％
以上０．４ｗｔ％以下に限定することにより、純ジルコ
ニウム相当の軟質な機械的強度を有する高温高圧水蒸気
雰囲気中での水素吸収特性及び耐応力腐食割れ性に優れ
た軟質ジルコニウム合金を得ている。If the Fe content in the soft zirconium alloy is less than 0.1 wt%, the corrosion resistance is not sufficiently improved, and if it exceeds 0.4 wt%, the mechanical strength becomes higher than that of pure zirconium. Therefore, in the invention of claim 2,
The amount of Fe contained in the soft zirconium alloy is 0.1 wt%
By limiting the content to 0.4 wt% or less, a soft zirconium alloy excellent in hydrogen absorption properties and stress corrosion cracking resistance in a high-temperature and high-pressure steam atmosphere having soft mechanical strength equivalent to pure zirconium is obtained.
【００１５】[0015]
【実施例】スポンジジルコニウムにＦｅを添加した本発
明の高温高圧水蒸気雰囲気中での水素吸収特性及び耐応
力腐食割れ性に優れた軟質ジルコニウム合金（Ｎｏ．１
〜Ｎｏ．１３）を用いて、腐食試験（耐食性）、ビッカ
ース硬度の測定及び結晶粒度の測定を行った。DESCRIPTION OF THE PREFERRED EMBODIMENTS A soft zirconium alloy (No. 1) having excellent hydrogen absorption characteristics and stress corrosion cracking resistance in a high-temperature, high-pressure steam atmosphere of the present invention in which Fe is added to sponge zirconium.
-No. Using 13), a corrosion test (corrosion resistance), measurement of Vickers hardness, and measurement of crystal grain size were performed.
【００１６】腐食試験は、ＦｅとＮｉとの含有量がそれ
ぞれ異なる軟質ジルコニウム合金（Ｎｏ．１〜Ｎｏ．１
３）をそれぞれ６５ｍｍ×１５ｍｍ×１．０ｍｍの試験
片に成形し、４００℃、１０５気圧の高温高圧水蒸気下
で２４時間置いたものの腐食状態を検討し、腐食が全く
進んでいないものは◎、腐食しているが原子炉材料とし
て耐え得る程度のものは○、腐食が進んだものはＸとし
ている。In the corrosion test, soft zirconium alloys (No. 1 to No. 1) having different contents of Fe and Ni were used.
3) was molded into a test piece of 65 mm × 15 mm × 1.0 mm, and placed under high temperature and high pressure steam at 400 ° C. and 105 atm for 24 hours. The corrosion state was examined.の も の indicates that it is corrosive but can withstand as a reactor material, and X indicates that corrosion has advanced.
【００１７】また、ビッカース硬度は、上記軟質ジルコ
ニウム合金の試験片の試験面にダイヤモンド圧子でくぼ
みをつけることにより得られる指標であり、数値が大き
いほど機械的強度が大きくなる。The Vickers hardness is an index obtained by making a test surface of a test piece of the above soft zirconium alloy with a diamond indenter, and the larger the numerical value, the higher the mechanical strength.
【００１８】尚、比較のため、純ジルコニウム（Ｂ）
と、ジルカロイ−２（Ｐ）及びＦｅの含有量が０．８ｗ
ｔ％のもの（Ｎｏ．１４）についても同様の試験を行っ
た。その結果を表１に示す。For comparison, pure zirconium (B)
And the content of Zircaloy-2 (P) and Fe is 0.8 w
The same test was performed for the sample of t% (No. 14). Table 1 shows the results.
【００１９】[0019]
【表１】 [Table 1]
【００２０】表１よりもわかるように、Ｆｅの含有量が
０．１ｗｔ％のもの（Ｎｏ．１）は硬度の点では問題な
いが、耐食性が○である。Ｆｅの含有量が０．２ｗｔ％
のもの（Ｎｏ．２）の耐食性が◎であり、純ジルコニウ
ム（Ｂ）言い換えるとＦｅを全く含有していないものは
Ｘであることから、Ｆｅの含有量が０．１ｗｔ％よりも
少ないと耐食性が悪くなることが言える。As can be seen from Table 1, the alloy having a Fe content of 0.1 wt% (No. 1) has no problem in hardness, but has a corrosion resistance of ○. Fe content of 0.2 wt%
(No. 2) has a corrosion resistance of ◎, and pure zirconium (B), in other words, has no Fe, is X. Therefore, if the Fe content is less than 0.1 wt%, the corrosion resistance is Can be said to be worse.
【００２１】また、Ｆｅの含有量が０．８ｗｔ％のもの
（Ｎｏ．１４）は耐食性が○であるが、硬度がジルカロ
イ−２（Ｐ）よりもさらに高くなってしまうため好まし
くない。従って、耐食性という観点からはＦｅの含有量
については０．１ｗｔ％から０．６ｗｔ％までが好まし
い範囲といえる。Further, the alloy having a Fe content of 0.8 wt% (No. 14) has a corrosion resistance of ○, but is not preferable because its hardness is higher than that of Zircaloy-2 (P). Therefore, from the viewpoint of corrosion resistance, the content of Fe is preferably in the range of 0.1 wt% to 0.6 wt%.
【００２２】また、Ｆｅの含有量毎にＮｉの添加量を変
えたものについては、殆どがＮｉの添加量が増える度に
硬度が大きくなっていることがわかる。原子炉材料とし
て好ましいのはジルカロイ−２程度以下であるため、Ｎ
ｉの添加量を０．１ｗｔ％以上０．４ｗｔ％以下とする
と良いことがわかる。In addition, it can be seen that the hardness of each of the alloys in which the amount of Ni added was changed for each Fe content increased as the amount of Ni added increased. The preferred reactor material is Zircaloy-2 or less.
It can be seen that it is good to set the amount of i to be 0.1 wt% or more and 0.4 wt% or less.
【００２３】なお、結晶粒度（ＡＳＴＭ）は、ＦｅとＮ
ｉの総量が多くなればなるほど大きな値となることが言
える。結晶粒度（ＡＳＴＭ）もジルカロイ−２程度以下
とすることが好ましいため、ＦｅとＮｉの総添加量を
０．８ｗｔ％よりも少なくするとよい。The grain size (ASTM) of Fe and N
It can be said that the larger the total amount of i, the larger the value. Since the crystal grain size (ASTM) is also preferably about Zircaloy-2 or less, the total addition amount of Fe and Ni may be less than 0.8 wt%.
【００２４】また、本発明の軟質ジルコニウム合金（Ｎ
ｏ．１〜Ｎｏ．１３）のうち、Ｆｅのみが添加されてい
るもの、すなわち、Ｎｏ．１、Ｎｏ．２、Ｎｏ．６、Ｎ
ｏ．１１のそれぞれを１ａｔｍの水素ガス雰囲気中で３
５０℃１２時間置き、水素吸収量（ｍｇ／ｄｍ2 ）を測
定した。尚、比較検討のため、Ｆｅの含有量が０．８ｗ
ｔ％のもの（Ｎｏ．１４）、純ジルコニウム（Ｂ）、ジ
ルカロイ−２（Ｐ）についても同様の試験を行いそれぞ
れ水素吸収量を測定した。その結果を表２に示す。The soft zirconium alloy of the present invention (N
o. 1 to No. 13), only Fe is added, that is, No. 13 1, No. 2, No. 6, N
o. 11 in a hydrogen gas atmosphere of 1 atm.
The sample was placed at 50 ° C. for 12 hours, and the hydrogen absorption (mg / dm 2 ) was measured. For comparison, the Fe content was 0.8 w
The same test was carried out for the sample of t% (No. 14), pure zirconium (B), and zircaloy-2 (P), and the hydrogen absorption was measured. Table 2 shows the results.
【００２５】[0025]
【表２】 [Table 2]
【００２６】表２より、純ジルコニウム（Ｂ）の水素吸
収量に比べてジルカロイ−２は非常に大量の水素を吸収
しているが、Ｆｅを含むジルコニウムは、含有するＦｅ
の量によらず水素吸収特性が向上し、純ジルコニウム
（Ｂ）よりも水素吸収量が少なくなっていることがわか
る。From Table 2, it can be seen that zircaloy-2 absorbs a very large amount of hydrogen compared to the amount of hydrogen absorbed by pure zirconium (B).
It can be seen that the hydrogen absorption characteristics are improved irrespective of the amount of hydrogen and the hydrogen absorption is smaller than that of pure zirconium (B).
【００２７】また、Ｎｏ．２、Ｎｏ．６、Ｎｏ．１１、
Ｎｏ．１４を用いて高温ヨウ素ガス中での応力腐食割れ
試験を行った。高温ヨウ素ガスとしてヨウ素分圧が４０
０Ｐａのアルゴンガスを３５０℃としたものを用い、歪
み速度が１０-5／ｓｅｃの時の断面減少率（％）をそれ
ぞれの試料ついて測定した。なお、比較のためヨウ素分
圧が０Ｐａ、即ち全くヨウ素を含んでいないアルゴンガ
スを３５０℃としたものを用い、歪み速度が１０-5／ｓ
ｅｃの時の断面減少率（％）をそれぞれの試料ついて測
定した。この結果を図１に示す。In addition, No. 2, No. 6, no. 11,
No. Using No. 14, a stress corrosion cracking test in high temperature iodine gas was performed. High temperature iodine gas with iodine partial pressure of 40
The cross-sectional reduction rate (%) at a strain rate of 10 −5 / sec was measured for each sample using argon gas of 0 Pa at 350 ° C. For comparison, an iodine partial pressure of 0 Pa, that is, an argon gas containing no iodine at 350 ° C. was used, and the strain rate was 10 −5 / s.
The cross-sectional reduction rate (%) at ec was measured for each sample. The result is shown in FIG.
【００２８】図１より明らかなように、Ｆｅ含有量が
０．６ｗｔ％以下であればヨウ素の影響を全く受けてい
ないものとほぼ同等の断面減少率を示すが、Ｆｅ含有量
が０．６ｗｔ％よりも多くなると急激に断面減少率が減
少する。従って、Ｆｅの含有量を０．６ｗｔ％以下とす
れば、高温ヨウ素ガス中での応力腐食割れ性が良好とな
る。As is evident from FIG. 1, when the Fe content is 0.6 wt% or less, the cross-sectional reduction rate is almost the same as that without any influence of iodine, but the Fe content is 0.6 wt%. %, The cross-sectional reduction rate sharply decreases. Therefore, when the content of Fe is 0.6 wt% or less, the stress corrosion cracking property in high-temperature iodine gas is improved.
【００２９】[0029]
【発明の効果】以上のように、本発明では、Ｆｅの含有
量を０．１ｗｔ％以上０．６ｗｔ％以下とすることによ
り、高温高圧水蒸気雰囲気中での水素吸収特性及び耐応
力腐食割れ性に優れた軟質ジルコニウム合金となる。As described above, according to the present invention, by setting the Fe content to 0.1 wt% or more and 0.6 wt% or less, the hydrogen absorption property and the stress corrosion cracking resistance in a high-temperature and high-pressure steam atmosphere are obtained. It becomes a soft zirconium alloy excellent in quality.
【図１】高温ヨウ素ガス中での応力腐食割れ試験を行っ
た時のＦｅの含有量と断面減少率との関係を示すグラフ
である。FIG. 1 is a graph showing the relationship between the Fe content and the cross-sectional reduction rate when a stress corrosion cracking test was performed in a high-temperature iodine gas.
Claims (2)
０．１ｗｔ％以上０．６ｗｔ％以下のＦｅを含み、酸素
の含有量が1200ppm 以下、その他不可避不純物の含有量
が2000ppm 以下であることを特徴とする高温高圧水蒸気
雰囲気中での水素吸収特性及び耐応力腐食割れ性に優れ
た軟質ジルコニウム合金。1. A small amount additive in zirconium,
A hydrogen absorption characteristic in a high-temperature and high-pressure steam atmosphere, characterized by containing Fe of 0.1 wt% or more and 0.6 wt% or less, and having an oxygen content of 1200 ppm or less and other unavoidable impurities of 2000 ppm or less; Soft zirconium alloy with excellent stress corrosion cracking resistance.
ｗｔ％以下であることを特徴とする請求項１に記載の高
温高圧水蒸気雰囲気中での水素吸収特性及び耐応力腐食
割れ性に優れた軟質ジルコニウム合金。2. The method according to claim 1, wherein the content of Fe is at least 0.1 wt% and at least 0.4 wt.
2. The soft zirconium alloy according to claim 1, which is excellent in hydrogen absorption characteristics and stress corrosion cracking resistance in a high-temperature high-pressure steam atmosphere.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP9039702A JPH10219376A (en) | 1997-02-10 | 1997-02-10 | Soft zirconium alloy excellent in hydrogen absorbing characteristic and stress corrosion cracking resistance in high temperature-high pressure water vapor atmosphere |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP9039702A JPH10219376A (en) | 1997-02-10 | 1997-02-10 | Soft zirconium alloy excellent in hydrogen absorbing characteristic and stress corrosion cracking resistance in high temperature-high pressure water vapor atmosphere |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH10219376A true JPH10219376A (en) | 1998-08-18 |
Family
ID=12560353
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP9039702A Pending JPH10219376A (en) | 1997-02-10 | 1997-02-10 | Soft zirconium alloy excellent in hydrogen absorbing characteristic and stress corrosion cracking resistance in high temperature-high pressure water vapor atmosphere |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH10219376A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2005272906A (en) * | 2004-03-24 | 2005-10-06 | Nikko Materials Co Ltd | Hydrogen occlusion alloy |
| JP2011021276A (en) * | 2010-09-01 | 2011-02-03 | Jx Nippon Mining & Metals Corp | Hydrogen storage alloy |
-
1997
- 1997-02-10 JP JP9039702A patent/JPH10219376A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2005272906A (en) * | 2004-03-24 | 2005-10-06 | Nikko Materials Co Ltd | Hydrogen occlusion alloy |
| JP2011021276A (en) * | 2010-09-01 | 2011-02-03 | Jx Nippon Mining & Metals Corp | Hydrogen storage alloy |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN101270426B (en) | Zirconium based alloy for nuclear reactor | |
| JP4099493B2 (en) | Zirconium alloy composition with excellent creep resistance | |
| JP4536119B2 (en) | Elements for use in nuclear reactors, comprising a zirconium-based alloy having creep resistance and corrosion resistance to water and water vapor, and a method for producing the same | |
| US5254308A (en) | Zirconium alloy with improved post-irradiation properties | |
| GB2023651A (en) | Iron-nickel-chromium age-hardenable alloys | |
| US5196163A (en) | Highly corrosion-resistant zirconium alloy for use as nuclear reactor fuel cladding material | |
| CN101285140A (en) | Zirconium based alloy as structural material of nuclear reactor core | |
| EP0776379B1 (en) | Nuclear fuel element for a pressurized-water reactor | |
| JPH10219376A (en) | Soft zirconium alloy excellent in hydrogen absorbing characteristic and stress corrosion cracking resistance in high temperature-high pressure water vapor atmosphere | |
| JPH0660364B2 (en) | Corrosion resistant zirconium alloy containing bismuth | |
| US5712888A (en) | Alloy for improved hydriding resistance and corrosion resistance nuclear reactor components | |
| US2987394A (en) | Iron-aluminum base alloys | |
| US4863685A (en) | Corrosion resistant zirconium alloys | |
| US2924518A (en) | Zirconium alloys | |
| JPH08253828A (en) | Highly corrosion resistant zirconium alloy | |
| US3597193A (en) | Vanadium base alloy | |
| JPH01301830A (en) | High corrosion-resistant zirconium alloy | |
| EP0779936B1 (en) | Zirconium alloy with tungsten and nickel | |
| US20020129878A1 (en) | Cr-base heat resisting alloy | |
| JP2726299B2 (en) | High corrosion resistant zirconium alloy for nuclear reactors | |
| EP1136578B1 (en) | Zirconium alloy for nuclear fuel assembly | |
| JPH02173235A (en) | Corrosion resisting zirconium alloy | |
| EP0287888B1 (en) | Corrosion resistant zirconium alloys | |
| JPH024937A (en) | Zr alloy for reactor fuel assembled body | |
| EP0501938A1 (en) | Zirconium-gallium alloy and structural components made thereof for use in nuclear reactors |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| A02 | Decision of refusal |
Free format text: JAPANESE INTERMEDIATE CODE: A02 Effective date: 20011016 |