JPH024937A - Zr alloy for reactor fuel assembled body - Google Patents
Zr alloy for reactor fuel assembled bodyInfo
- Publication number
- JPH024937A JPH024937A JP1010448A JP1044889A JPH024937A JP H024937 A JPH024937 A JP H024937A JP 1010448 A JP1010448 A JP 1010448A JP 1044889 A JP1044889 A JP 1044889A JP H024937 A JPH024937 A JP H024937A
- Authority
- JP
- Japan
- Prior art keywords
- alloy
- reactor fuel
- strength
- corrosion resistance
- resistance
- 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
- 239000003758 nuclear fuel Substances 0.000 title claims abstract description 18
- 229910001093 Zr alloy Inorganic materials 0.000 title abstract description 20
- 229910052715 tantalum Inorganic materials 0.000 claims abstract description 8
- 229910052750 molybdenum Inorganic materials 0.000 claims abstract description 7
- 229910052804 chromium Inorganic materials 0.000 claims abstract description 5
- 229910052742 iron Inorganic materials 0.000 claims abstract description 4
- 239000000203 mixture Substances 0.000 claims description 8
- 230000000712 assembly Effects 0.000 claims description 7
- 238000000429 assembly Methods 0.000 claims description 7
- 239000012535 impurity Substances 0.000 claims description 3
- 229910052726 zirconium Inorganic materials 0.000 claims description 2
- 238000005260 corrosion Methods 0.000 abstract description 21
- 230000007797 corrosion Effects 0.000 abstract description 21
- 238000005253 cladding Methods 0.000 abstract description 5
- 229910052758 niobium Inorganic materials 0.000 abstract description 5
- 229910052720 vanadium Inorganic materials 0.000 abstract description 4
- 229910052718 tin Inorganic materials 0.000 abstract 2
- -1 etc. Inorganic materials 0.000 abstract 1
- 239000007858 starting material Substances 0.000 abstract 1
- 230000000694 effects Effects 0.000 description 8
- 239000000463 material Substances 0.000 description 8
- 238000012360 testing method Methods 0.000 description 8
- 239000000843 powder Substances 0.000 description 7
- 229910045601 alloy Inorganic materials 0.000 description 6
- 239000000956 alloy Substances 0.000 description 6
- 238000005096 rolling process Methods 0.000 description 5
- 238000005452 bending Methods 0.000 description 4
- 230000000052 comparative effect Effects 0.000 description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 3
- 238000005097 cold rolling Methods 0.000 description 2
- 239000000470 constituent Substances 0.000 description 2
- 230000007423 decrease Effects 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- 239000002994 raw material Substances 0.000 description 2
- 238000010521 absorption reaction Methods 0.000 description 1
- 238000000137 annealing Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000005242 forging Methods 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 238000005098 hot rolling Methods 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- 238000005554 pickling Methods 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
- 238000010791 quenching Methods 0.000 description 1
- 230000000171 quenching effect Effects 0.000 description 1
- 238000001953 recrystallisation Methods 0.000 description 1
- 238000011160 research Methods 0.000 description 1
- 238000009864 tensile test Methods 0.000 description 1
- 230000004584 weight gain Effects 0.000 description 1
- 235000019786 weight gain Nutrition 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 Steel (AREA)
Abstract
Description
【発明の詳細な説明】
〔産業上の利用分野〕
この発明は、特に高温高圧水や高温高圧水蒸気にさらさ
れる原子炉燃料被覆管や上記原子炉燃料被覆管を多数本
一定間隔をおいて支持する支持格子（以下、原子炉燃料
被覆管および上記原子炉燃料被覆管を支持する支持格子
を総称して原子炉燃料集合体という）に用いた場合に、
すぐれた耐食性、強度および耐緩和性を示すＺｒ合金に
関するものである。[Detailed Description of the Invention] [Industrial Application Field] This invention particularly relates to reactor fuel cladding tubes that are exposed to high-temperature, high-pressure water or high-temperature, high-pressure steam, and to support a large number of the above-mentioned nuclear fuel cladding tubes at regular intervals. When used in a support grid (hereinafter, a reactor fuel cladding tube and a support grid that supports the above-mentioned reactor fuel cladding tube are collectively referred to as a reactor fuel assembly),
This invention relates to a Zr alloy that exhibits excellent corrosion resistance, strength, and relaxation resistance.
従来、一般に、原子力発電プラントの原子炉に加圧水型
（ＰＷＲ）のものがあり、この原子炉の原子炉燃料集合
体の製造にはＺｒ合金が用いられ、このＺｒ合金の代表
的なものとして、重量％で（以Ｆ％は重量％を示す）、
Ｓｎ ： １．２−１．７％。Conventionally, there are pressurized water type (PWR) reactors in nuclear power plants, and Zr alloys are used to manufacture reactor fuel assemblies for these reactors, and typical examples of these Zr alloys include: In weight% (hereinafter F% indicates weight%), Sn: 1.2-1.7%.
Ｆｅ ： ０．１８〜０．２４％。Fe: 0.18-0.24%.
Ｃｒ ： ０．０７”０．ｌ１％。Cr: 0.07" 0.1%.
を含有し、残りがＺｒと不可避不純物からなる組成を有
するジルカロイ−４が使用されていることは良く知られ
るところである。It is well known that Zircaloy-4 is used, which has a composition of Zr and unavoidable impurities.
つ
〔発明が解決しようとする課題〕
一方、近年、原子力発電プラントの経済性向上のための
燃料の高燃焼度化に伴って、原子炉燃料集合体の炉内滞
在時間が長期化する傾向にあるが、上記従来のＺｒ合金
で作られた原子炉燃料集合体では、耐食性、強度および
耐緩和性（クリープ特性）が十分てないことに原因して
、これに対応することかできないのが現状であった。[Problem to be solved by the invention] On the other hand, in recent years, as fuel burn-up has been increased to improve the economic efficiency of nuclear power plants, there has been a tendency for nuclear reactor fuel assemblies to stay in the reactor for a longer time. However, the current state of the art is that nuclear reactor fuel assemblies made from the conventional Zr alloys described above do not have sufficient corrosion resistance, strength, and relaxation resistance (creep properties), and are unable to cope with this problem. Met.
そこで、本発明者等は、上述のような観点から、原子燃
料集合体として用いた場合に、−層すくれた耐食性、強
度および耐緩和性（クリープ特性）を示すＺｒ合金を開
発すべく研究を行なった結果、
上記従来のＺ「合金において、Ｓｎ含有量を相対的に低
くした状態で、ＮｂおよびＴａを含有させると、−段と
耐食性が向上するようになり、さらにＶおよびＭｏを含
有させると、強度および耐緩和性（クリープ特性）の改
善がみられるようになり、原子炉燃料集合体として用い
た場合に長期に亘る使用が可能になるという知見を得た
のである。Therefore, from the above-mentioned viewpoint, the present inventors conducted research to develop a Zr alloy that exhibits excellent corrosion resistance, strength, and relaxation resistance (creep properties) when used as a nuclear fuel assembly. As a result, we found that when Nb and Ta were added to the conventional Z alloy with a relatively low Sn content, the corrosion resistance was significantly improved, and when V and Mo were added, By doing so, they found that the strength and relaxation resistance (creep properties) were improved, and that when used as a nuclear reactor fuel assembly, it could be used for a long period of time.
したがって、この発明は、上記知見にもとづいてなされ
たものであって、
Ｓｎ ： ０．２〜１．７ ％、 Ｆｅ ：
０．１８−０．Ｂ ％。Therefore, this invention was made based on the above findings, and includes Sn: 0.2 to 1.7%, Fe:
0.18-0. B%.
Ｃｒ ： ０．０’７”０．４ ％。Cr: 0.0’7”0.4%.
を含有し、
Ｎｂ：０．０５〜１％、 Ｔａ ： ０．０１〜
０．２％。Nb: 0.05~1%, Ta: 0.01~
0.2%.
のうちの１種または、２種を含有し、さらに、Ｖ：０．
０５〜１％、 Ｍｏ ： ０．０５〜１％。Contains one or two of the following, and further contains V: 0.
05-1%, Mo: 0.05-1%.
のうちの１種または２種を含有し、残りがＺｒと不可避
不純物からなる組成を有する耐食性、強度および耐緩和
性（クリープ特性）のすぐれた原子炉燃料集合体用Ｚｒ
合金に特徴を有するものである。Zr for nuclear reactor fuel assemblies with excellent corrosion resistance, strength and relaxation resistance (creep properties), containing one or two of the following, with the remainder consisting of Zr and unavoidable impurities.
The alloy has characteristics.
つぎに、この発明のＺｒ合金において、成分組成範囲を
上記の通りに限定した理由を説明する。Next, the reason why the composition range of the Zr alloy of the present invention is limited as described above will be explained.
（ａ） ５ｎ
Ｓｎ成分には、合金の強度を向上させる作用があるが、
その含有量が０．２％未満では所定の強度および耐緩和
性（クリープ特性）を確保することかできず、一方その
含有量が１．７％を越えると、耐食性の著しい低下をき
たすようになることから、その含有量を０．２〜１．７
％と定めた。(a) The 5n Sn component has the effect of improving the strength of the alloy, but
If the content is less than 0.2%, it will not be possible to secure the desired strength and relaxation resistance (creep properties), while if the content exceeds 1.7%, the corrosion resistance will be significantly reduced. Therefore, the content should be 0.2 to 1.7
%.
（ｂ）’ＦｃおよびＣｒ
これらの成分には、共存した状態で合金の耐食性と強度
を向上させる作用があるが、その含有量がそれぞれＦ
ｃ：０．１８％未満およびＣｒ：Ｏ，Ｏ’７％未満では
前記作用に所望の効果が得られず、一方その含有量がＦ
ｅ：０．６％およθＣｒ：０．４％を越えると、耐食
性が著しく低下するようになることから、その含有量を
それぞれＦ ｅ：ｏ、１８〜０．８％、Ｃｒ：０．０７
〜０．４％と定めた。(b)'Fc and Cr These components have the effect of improving the corrosion resistance and strength of the alloy when they coexist, but their content is Fc and Cr.
c: less than 0.18% and Cr:O,O'7%, the desired effect cannot be obtained;
If e: 0.6% and θCr: 0.4% are exceeded, the corrosion resistance will be significantly reduced, so the contents should be adjusted to Fe: o, 18 to 0.8%, Cr: 0. 07
It was set at ~0.4%.
（ｃ）ＮｂおよびＴａ
これらの成分には、合金の耐食性を一段と向上させる作
用があるが、その含有量がそれぞれＮｂ：００５％未満
およびＴａ：０．０１％未満では所望の耐食性向上効果
か得られず、一方Ｎｂの含有量が１％を越えると耐食性
が低下するようになり、またＴａ含有量が０．２％を越
えても耐食性向上があまりなく、中性子吸収が増大する
ことから、それらの含有量をそれぞれＮｂ：０．０５〜
１％、 Ｔａ：０．０１〜０．２％と定めた。(c) Nb and Ta These components have the effect of further improving the corrosion resistance of the alloy, but if their content is less than 0.05% Nb and less than 0.01% Ta, the desired corrosion resistance improvement effect cannot be obtained. On the other hand, when the Nb content exceeds 1%, the corrosion resistance decreases, and even when the Ta content exceeds 0.2%, there is little improvement in corrosion resistance and neutron absorption increases. The content of Nb: 0.05~
1%, and Ta: 0.01 to 0.2%.
（ｄ） ＶおよびＭＯ
これらの成分には、合金の強度および耐緩和性（クリー
プ特性）を向上させる作用があるが、その含有量がそれ
ぞれＶ ： ０．０５％未満およびＭＯ：０．０５％未
満では所望の強度および耐緩和性（クリープ特性）向上
効果が得られず、一方その含有量がそれぞれｖ：１％お
よびＭｏ：１％を越えると耐食性が低下するようになる
ことから、その含有量をＶ：０．０５−１％、 Ｍｏ：
０．０５〜１％と定めた。(d) V and MO These components have the effect of improving the strength and relaxation resistance (creep properties) of the alloy, but their contents are V: less than 0.05% and MO: 0.05%, respectively. If the content is less than 1%, the desired effect of improving strength and relaxation resistance (creep properties) cannot be obtained, while if the content exceeds v: 1% and Mo: 1%, corrosion resistance will decrease. The amount is V: 0.05-1%, Mo:
It was set at 0.05-1%.
つぎに、この発明のＺｒ合金を実施例により具体的に説
明する。Next, the Zr alloy of the present invention will be specifically explained using examples.
溶解原料として、９９．８％以上の各種の純度を有する
Ｚｒスポンジ、いずれも９９．９％以上の純度を有する
Ｓｎ粉末、Ｆｅ粉末、Ｃｒ粉末、Ｎｂ粉末、Ｔａ粉末、
■粉末、およびＭｏ粉末を用意し、これら原料を所定の
配合組成に配合し、混合した後、アーク炉にて溶解して
ボタン材とし、ついてこのホタン材に、温度： １０１
０℃に１５分間保持した後、熱間鍛造を施し、再び１０
１０℃に加熱後、水焼入れを行ない、さらに機械加工に
より酸化スケールを除去した後、温度＝６００℃、圧延
率＝５０％の条件で熱間圧延を行ない、引続いて酸洗し
て酸化スケールを除去した後、５０％の圧延率で冷間圧
延を行ない、ついで温度：５５０〜７５０℃に２時間保
持の条件で再結晶焼鈍を行ない、再び５０％の圧延率て
冷間圧延を行なうことによって、それぞれ第１表に示さ
れる組成を有し、かつ厚さがいずれも０．５ｍｍの本発
明Ｚｒ合金板材１〜２０、比較Ｚｒ合金板材１〜１５お
よび従来Ｚｒ合金（ジルカロイ−４）板材をそれぞれ製
造した。As melting raw materials, Zr sponge with various purity of 99.8% or more, Sn powder, Fe powder, Cr powder, Nb powder, Ta powder, all of which have purity of 99.9% or more,
■Prepare powder and Mo powder, blend these raw materials into a predetermined composition, mix, melt in an arc furnace to make a button material, and then add to this hotane material at a temperature of 101
After being held at 0°C for 15 minutes, hot forging was performed and the temperature was heated again at 10°C.
After heating to 10°C, water quenching was performed, and oxidized scale was removed by mechanical processing, followed by hot rolling at a temperature of 600°C and a rolling ratio of 50%, followed by pickling to remove oxidized scale. After removing, cold rolling is performed at a rolling ratio of 50%, followed by recrystallization annealing at a temperature of 550 to 750°C for 2 hours, and cold rolling is performed again at a rolling ratio of 50%. Zr alloy plates 1 to 20 of the present invention, comparative Zr alloy plates 1 to 15, and conventional Zr alloy (Zircaloy-4) plates each having the composition shown in Table 1 and having a thickness of 0.5 mm. were manufactured respectively.
なお、比較Ｚｒ合金板材１〜１５は、いずれも構成成分
のうちのいずれかの成分含有量（第１表に※印を付す）
かこの発明の範囲から外れた組成をもつものである。In addition, comparative Zr alloy sheets 1 to 15 all have the content of one of the constituent components (marked with * in Table 1).
However, it has a composition outside the scope of this invention.
ついで、この結果得られた各種の板材から、２０＋ｎｍ
Ｘ２５ｍｍの＝Ｊ’法を有し、かつ長手方向片側から５
ｍｍのところに直径：３ｍｍの小孔を有する試験片を切
り出し、通常の静置式オートクレーブ装置を用い、温度
：４００℃、圧カニ１０５ｋｇ／ｃシの高温高圧水蒸気
中の原子炉燃料集合体がさらされる条件で炉外腐食試験
を行ない、１２０日経過後の腐食増量を測定した。Next, from the various plate materials obtained as a result, 20+nm
X25mm = J' method, and 5 from one side in the longitudinal direction
A test piece with a small hole of 3 mm in diameter was cut out, and the reactor fuel assembly was exposed to high-temperature, high-pressure steam at a temperature of 400°C and a pressure of 105 kg/c using a normal stationary autoclave. An outside-furnace corrosion test was conducted under the following conditions, and the increase in corrosion weight after 120 days was measured.
また、上記の各種の板材から、平行部長さ＝３２ｍｍ、
平行部幅： ６．２５±０．０５關、長さ：１００＋＋
＋ｍの寸法をもった試験片を切り出し、インストロン型
引張試験装置を用いて、常温引張強さを測定した。Also, from the above various plate materials, the parallel length = 32 mm,
Parallel width: 6.25±0.05, length: 100++
A test piece having a dimension of +m was cut out, and its room temperature tensile strength was measured using an Instron type tensile testing device.
さらに、上記各種の板材から、幅：５±０．０１ｍｍ、
長さ＝１００±０．２ｍｍの寸法をもった試験片を、上
記幅が圧延方法に平行にかつ上記長さが圧延方向に垂直
になるように切り出し、上記切り出した試験片に曲げの
初期応力σ。： ２４．［ｆｋｇ／−を付与しながら温
度＝４００℃、２４０時間保持の応力緩和試験したのち
、再び試験片の曲げ応力σを測定し、応力緩和試験後の
曲げ応カニσに対する初期曲げ応カニσ０の比；
＝非応力緩和比
σ０
をもって耐緩和性を評価した。この非応力緩和比が１．
０に近いほど耐緩和性がすぐれていることになり、原子
炉燃料集合体の材料としてすぐれていることを示す。Furthermore, from the above various plate materials, width: 5 ± 0.01 mm,
A test piece with length = 100 ± 0.2 mm was cut out so that the above width was parallel to the rolling method and the above length was perpendicular to the rolling direction, and the cut out test piece was given an initial bending stress. σ. : 24. After conducting a stress relaxation test at a temperature of 400°C and holding for 240 hours while applying fkg/-, the bending stress σ of the test piece was measured again, and the initial bending stress σ0 was compared to the bending stress σ after the stress relaxation test. The relaxation resistance was evaluated using the ratio: = non-stress relaxation ratio σ0. This non-stress relaxation ratio is 1.
The closer it is to 0, the better the relaxation resistance is, indicating that it is an excellent material for nuclear reactor fuel assemblies.
上記腐食増量、常温引張強さおよび非応力緩和比の測定
結果を第１表に示した。Table 1 shows the measurement results of the corrosion weight gain, room temperature tensile strength, and non-stress relaxation ratio.
第１表に示される結果から、本発明Ｚｒ合金板ｔｉＡ’
１〜２０は、いずれも従来Ｚｒ合金（ジルカロイ−４
）板材よりもすぐれた耐食性、強度および耐緩和性を示
し、さらに、比較Ｚｒ合金板材１〜１５にみられるよう
に、構成成分のうちのいずれかの成分含有足でもこの発
明の範囲から外れると、耐食性、強度および耐緩和性の
うちの少なくともいずれかが低下するようになることが
明らかである。From the results shown in Table 1, it can be seen that the present invention Zr alloy plate tiA'
Nos. 1 to 20 are all conventional Zr alloys (Zircaloy-4
) exhibits better corrosion resistance, strength and relaxation resistance than sheet materials, and furthermore, as seen in Comparative Zr alloy sheet materials 1 to 15, even the presence of any of the constituent components is outside the scope of the present invention. It is clear that at least one of corrosion resistance, strength, and relaxation resistance is reduced.
上述のように、この発明のＺｒ合金は、原子炉燃料集合
体がさらされる条件下ですぐれた耐食性、強度および耐
緩和性を示すので、これを実用に供した場合には著しく
長期に亘っての使用が可能となるなど工業上有用な特性
を有するものである。As mentioned above, the Zr alloy of the present invention exhibits excellent corrosion resistance, strength, and relaxation resistance under the conditions to which nuclear reactor fuel assemblies are exposed, so that when it is put into practical use, it will last for an extremely long period of time. It has industrially useful properties such as being able to be used for.
Claims (1)
６％、Ｃｒ：０．０７〜０．４％、 を含有し、 Ｎｂ：０．０５〜１％、Ｔａ：０．０１〜０．２％、の
うちの１種または２種を含有し、さらに、Ｖ：０．０５
〜１％、Ｍｏ：０．０５〜１％、のうちの１種または２
種を含有し、残りがＺｒと不可避不純物からなる組成（
以上重量％）を有することを特徴とする原子炉燃料集合
体用Ｚｒ合金。(1) Sn: 0.2-1.7%, Fe: 0.18-0.
6%, Cr: 0.07-0.4%, Contains one or two of Nb: 0.05-1%, Ta: 0.01-0.2%, Furthermore, V: 0.05
~1%, Mo: 0.05~1%, one or two of them
A composition containing seeds and the remainder consisting of Zr and unavoidable impurities (
% by weight) for use in nuclear reactor fuel assemblies.
Priority Applications (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR898900713A FR2626291B1 (en) | 1988-01-22 | 1989-01-20 | ZIRCONIUM-BASED ALLOY FOR USE AS A FUEL ASSEMBLY IN A NUCLEAR REACTOR |
| US07/558,797 US5017336A (en) | 1988-01-22 | 1990-07-26 | Zironium alloy for use in pressurized nuclear reactor fuel components |
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1232488 | 1988-01-22 | ||
| JP63-12324 | 1988-01-22 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH024937A true JPH024937A (en) | 1990-01-09 |
| JP2687538B2 JP2687538B2 (en) | 1997-12-08 |
Family
ID=11802133
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1010448A Expired - Lifetime JP2687538B2 (en) | 1988-01-22 | 1989-01-19 | Zr alloy for nuclear reactor fuel assemblies |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2687538B2 (en) |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR100261666B1 (en) * | 1998-02-04 | 2000-07-15 | 장인순 | Composition of zirconium alloy having low corrosion rate and high strength |
| JP2006028553A (en) * | 2004-07-13 | 2006-02-02 | Toshiba Corp | Zirconium alloy and channel box utilizing the same |
| JP2010145326A (en) * | 2008-12-22 | 2010-07-01 | Global Nuclear Fuel-Japan Co Ltd | Zirconium base alloy, fuel assembly for water-cooled nuclear power reactor using the same, and channel box |
| WO2010147814A2 (en) | 2009-06-15 | 2010-12-23 | The Dial Corporation | Combinations of herb extracts having synergistic antioxidant effect, and methods relating thereto |
| CN105543560A (en) * | 2016-01-06 | 2016-05-04 | 中国核动力研究设计院 | Zirconium alloy for nuclear reactor |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS61170552A (en) * | 1985-01-22 | 1986-08-01 | ウエスチングハウス エレクトリック コ−ポレ−ション | Production of article comprising zirconium-niobium alloy containing tin and third alloy element |
| JPS61174347A (en) * | 1985-01-30 | 1986-08-06 | Hitachi Ltd | Nodular corrosion resisting zirconium-base alloy |
| JPS6233734A (en) * | 1985-08-05 | 1987-02-13 | Hitachi Ltd | Zirconium alloy having high corrosion resistance |
| JPH01149932A (en) * | 1987-10-28 | 1989-06-13 | Westinghouse Electric Corp <We> | Production of zirconium alloy for liner of fuel element |
| JPH01301830A (en) * | 1988-05-30 | 1989-12-06 | Sumitomo Metal Ind Ltd | High corrosion-resistant zirconium alloy |
-
1989
- 1989-01-19 JP JP1010448A patent/JP2687538B2/en not_active Expired - Lifetime
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS61170552A (en) * | 1985-01-22 | 1986-08-01 | ウエスチングハウス エレクトリック コ−ポレ−ション | Production of article comprising zirconium-niobium alloy containing tin and third alloy element |
| JPS61174347A (en) * | 1985-01-30 | 1986-08-06 | Hitachi Ltd | Nodular corrosion resisting zirconium-base alloy |
| JPS6233734A (en) * | 1985-08-05 | 1987-02-13 | Hitachi Ltd | Zirconium alloy having high corrosion resistance |
| JPH01149932A (en) * | 1987-10-28 | 1989-06-13 | Westinghouse Electric Corp <We> | Production of zirconium alloy for liner of fuel element |
| JPH01301830A (en) * | 1988-05-30 | 1989-12-06 | Sumitomo Metal Ind Ltd | High corrosion-resistant zirconium alloy |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR100261666B1 (en) * | 1998-02-04 | 2000-07-15 | 장인순 | Composition of zirconium alloy having low corrosion rate and high strength |
| JP2006028553A (en) * | 2004-07-13 | 2006-02-02 | Toshiba Corp | Zirconium alloy and channel box utilizing the same |
| JP2010145326A (en) * | 2008-12-22 | 2010-07-01 | Global Nuclear Fuel-Japan Co Ltd | Zirconium base alloy, fuel assembly for water-cooled nuclear power reactor using the same, and channel box |
| WO2010147814A2 (en) | 2009-06-15 | 2010-12-23 | The Dial Corporation | Combinations of herb extracts having synergistic antioxidant effect, and methods relating thereto |
| CN105543560A (en) * | 2016-01-06 | 2016-05-04 | 中国核动力研究设计院 | Zirconium alloy for nuclear reactor |
Also Published As
| Publication number | Publication date |
|---|---|
| JP2687538B2 (en) | 1997-12-08 |
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