JPH0892700A - γ ', γ "phase precipitation strengthened high Ni steel - Google Patents

γ ', γ "phase precipitation strengthened high Ni steel

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Publication number
JPH0892700A
JPH0892700A JP6226307A JP22630794A JPH0892700A JP H0892700 A JPH0892700 A JP H0892700A JP 6226307 A JP6226307 A JP 6226307A JP 22630794 A JP22630794 A JP 22630794A JP H0892700 A JPH0892700 A JP H0892700A
Authority
JP
Japan
Prior art keywords
steel
less
temperature
irradiation
phase
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
Application number
JP6226307A
Other languages
Japanese (ja)
Inventor
Masahiko Morinaga
正彦 森永
Suminori Murata
純教 村田
Shigeharu Ukai
重治 鵜飼
Sakae Shikakura
栄 鹿倉
Makoto Harada
誠 原田
Toshio Nishida
俊夫 西田
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
TOYOHASHI GIJUTSU KAGAKU UNIV
Doryokuro Kakunenryo Kaihatsu Jigyodan
Power Reactor and Nuclear Fuel Development Corp
Original Assignee
TOYOHASHI GIJUTSU KAGAKU UNIV
Doryokuro Kakunenryo Kaihatsu Jigyodan
Power Reactor and Nuclear Fuel Development Corp
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by TOYOHASHI GIJUTSU KAGAKU UNIV, Doryokuro Kakunenryo Kaihatsu Jigyodan, Power Reactor and Nuclear Fuel Development Corp filed Critical TOYOHASHI GIJUTSU KAGAKU UNIV
Priority to JP6226307A priority Critical patent/JPH0892700A/en
Publication of JPH0892700A publication Critical patent/JPH0892700A/en
Pending legal-status Critical Current

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Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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  • Heat Treatment Of Steel (AREA)

Abstract

(57)【要約】 【目的】 耐スエリング性と高温クリープ強度、延性、
照射下での相安定性についてバランスのとれた高Niオ
ーステナイト鋼を提供する。 【構成】 重量%でSi:0.5%以下、Mn:1.0
%以下、Cr:13%〜18%、Ni:30〜50%、
Mo+W=2.0〜6.0、Al=0.05〜1.0
%、Ti=0.05〜0.6%、Nb=2〜5%、残部
がFe及び不可避不純物からなることを特徴とする
γ’,γ”相析出強化型高Ni鋼。
(57) [Summary] [Purpose] Swelling resistance, high temperature creep strength, ductility,
Provide a high Ni austenitic steel balanced in phase stability under irradiation. [Structure] Si: 0.5% or less by weight%, Mn: 1.0
% Or less, Cr: 13% to 18%, Ni: 30 to 50%,
Mo + W = 2.0 to 6.0, Al = 0.05 to 1.0
%, Ti = 0.05 to 0.6%, Nb = 2 to 5%, and the balance being Fe and inevitable impurities, γ ′, γ ″ phase precipitation strengthening high Ni steel.

Description

【発明の詳細な説明】Detailed Description of the Invention

【0001】[0001]

【産業上の利用分野】本発明は高Ni鋼、特に原子炉
(特に高速増殖炉)の炉心環境で長時間使用される炉心
構成要素(例えば燃料被覆管やラッパ管からなる燃料集
合体、制御棒、反射体等)や機器構造物(例えば、機器
容器部材、冷却系配管部材等)のように優れた耐中性子
照射特性が必要とされる高Ni鋼に関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a high Ni steel, in particular, a core component (for example, a fuel assembly including a fuel cladding tube or a trumpet tube) that is used for a long time in a core environment of a nuclear reactor (especially fast breeder reactor) The present invention relates to a high Ni steel such as a rod, a reflector or the like) or a device structure (for example, a device container member, a cooling system piping member, etc.) that requires excellent neutron resistance.

【0002】[0002]

【従来の技術】従来より炉心構成部材としては、SUS
316の他に、当該SUS316の高Ni化を図った改
良鋼が用いられてきた。これは、SUS316の耐照射
特性を改善するためであり、これまでのFe−Cr−N
i系合金の照射試験結果では、ボイドスエリングに対し
てNiの組成依存性が認められ、例えばFe−15Cr
合金では、45%Niでスエリング量が最低となること
が報告されているからである。
2. Description of the Related Art Conventionally, SUS has been used as a core constituent member.
In addition to 316, an improved steel for increasing the Ni content of the SUS316 has been used. This is to improve the irradiation resistance property of SUS316, and the conventional Fe-Cr-N
In the irradiation test result of the i-based alloy, the compositional dependence of Ni on the void swelling is recognized, and for example, Fe-15Cr
This is because it has been reported that the alloy has the lowest swelling amount at 45% Ni.

【0003】しかしながら、この一方で、Ni量を増加
させると高温強度が低下するので、耐照射特性改善のた
めに単純に高Ni化を図るのは妥当でない。そこで、耐
スエリング特性を向上させながら、高温強度を改善する
には、高Ni化以外に何らかの工夫を加える必要があ
る。現在のところ、炭窒化物の微細析出による強化と固
溶強化を組み合わせた材料(特願平6−39391号)
や、PE16のようにγ’の析出により強化した材料な
どが実用炉の候補材料として考えられている。
On the other hand, on the other hand, when the amount of Ni is increased, the high temperature strength decreases, so it is not appropriate to simply increase the Ni in order to improve the irradiation resistance characteristics. Therefore, in order to improve the high temperature strength while improving the swelling resistance, it is necessary to add some measure other than the high Ni content. Currently, a material that combines strengthening by fine precipitation of carbonitride and solid solution strengthening (Japanese Patent Application No. 6-39391).
Alternatively, a material such as PE16 reinforced by precipitation of γ ′ is considered as a candidate material for a practical furnace.

【0004】[0004]

【発明が解決しようとする課題】しかし、実用炉で想定
しているような高温、高速中性子、高応力下という厳し
い環境下という条件を完全に満足するる材料は現状では
開発されていない。例えば、Ni量が少ないと耐スエリ
ング性が問題となり、逆に耐スエリング性向上のためN
i量を50%以上添加すると、He脆化が問題となる。
また、本発明者らが過去開発した炭窒化物析出強化鋼
(特願平6−39391号)は、優れた相安定性を有す
るが、炭素(C)、窒素(N)がNiに固溶しにくいた
め高温強度を保ったままNi量を上げることが困難とな
り、発明で達成した強度が限界である。一方Ninom
ic PE16はFe−Ni基材料をγ’により析出強
化した材料であり、優れた高温強度を有するが、照射誘
起粒界析出脆化が問題となっている(なお、Ninom
ic PE16における照射誘起粒界析出脆化というの
は、中性子照射を受けるとγ’が粒界に再析出し、延性
が全くなくなってしまう現象である)。Tiを多く含む
ようなINCONEL706では、照射によりγ’が溶
けて粒界にη相(Ni3 Ti)が再析出し、脆化するこ
とが知られている。また、これらの問題を解決するた
め、単純にγ’+γ”量を10vol.%以下に抑える
ことも考えられるが、γ’,γ”の固溶化温度が下が
り、750℃を越えると急激に高温強度が低下するとい
う問題が生じる。
However, at present, no material has been developed which completely satisfies the conditions of a severe environment such as high temperature, fast neutrons and high stress, which are assumed in a practical reactor. For example, when the amount of Ni is small, the swelling resistance becomes a problem, and conversely, N is added to improve the swelling resistance.
When the i amount is 50% or more, He embrittlement becomes a problem.
Further, although the carbonitride precipitation strengthened steel (Japanese Patent Application No. 6-39391) developed by the present inventors has excellent phase stability, carbon (C) and nitrogen (N) are solid-dissolved in Ni. Since it is difficult to do so, it becomes difficult to increase the amount of Ni while maintaining the high temperature strength, and the strength achieved by the invention is the limit. Meanwhile, Ninom
ic PE16 is a material obtained by precipitation-strengthening an Fe-Ni-based material with γ'and has excellent high-temperature strength, but irradiation-induced grain boundary precipitation embrittlement poses a problem (note that Ninom).
Irradiation-induced grain boundary precipitation embrittlement in ic PE16 is a phenomenon in which γ'reprecipitates at grain boundaries upon neutron irradiation, and ductility is completely lost). It is known that in INCONEL 706 containing a large amount of Ti, γ ′ is melted by irradiation and the η phase (Ni 3 Ti) is reprecipitated at the grain boundaries to cause embrittlement. Further, in order to solve these problems, it is possible to simply suppress the amount of γ '+ γ "to 10 vol.% Or less, but the solution temperature of γ', γ" decreases, and when it exceeds 750 ° C, the temperature rapidly increases. There is a problem that the strength is lowered.

【0005】本発明では、以上のような問題点を解決
し、耐スエリング性と高温クリープ強度、延性、照射下
での相安定性についてバランスのとれた高Niオーステ
ナイト鋼を提供することを目的とする。
An object of the present invention is to solve the above problems and to provide a high Ni austenitic steel in which swelling resistance, high temperature creep strength, ductility and phase stability under irradiation are well balanced. To do.

【0006】[0006]

【課題を解決するための手段】本発明では、上記問題点
を解決するために、相安定性と高温強度の観点につい
て、d電子合金設計理論(特願平2−25622参
照)、試作−評価を基に鋭意研究した結果、以下のよう
な高Ni鋼を発明した。
In order to solve the above problems, in the present invention, in view of phase stability and high temperature strength, d electronic alloy design theory (see Japanese Patent Application No. 2-25622), trial production-evaluation. As a result of intensive research based on the above, the following high Ni steel was invented.

【0007】(1) 重量%でSi:0.5%以下、M
n:1.0%以下、Cr:13〜18%、Ni:30〜
50%、Mo+W=2.0〜6.0%、Al=0.05
〜1.0%、Ti=0.05〜0.6%、Nb=2〜5
%、残部がFe及び不可避不純物からなることを特徴と
する耐照射特性と高温強度、延性に優れたγ’,γ”相
析出強化型高Ni鋼。
(1) Si by weight%: 0.5% or less, M
n: 1.0% or less, Cr: 13-18%, Ni: 30-
50%, Mo + W = 2.0 to 6.0%, Al = 0.05
~ 1.0%, Ti = 0.05-0.6%, Nb = 2-5
%, The balance being Fe and unavoidable impurities, and a γ ′, γ ″ phase precipitation strengthened high Ni steel excellent in irradiation resistance, high temperature strength and ductility.

【0008】(2) 上記項目1記載の高Ni鋼におい
て、0.08%以下のPが添加されていることを特徴と
する高Ni鋼。
(2) A high Ni steel according to item 1 above, wherein 0.08% or less of P is added.

【0009】(3) 上記項目1または2記載の高Ni
鋼において、0.01%以下のBが添加されていること
を特徴とする高Ni鋼。
(3) High Ni according to item 1 or 2 above
A high Ni steel, characterized in that 0.01% or less of B is added to the steel.

【0010】(4) 上記項目1乃至3いずれか記載の
γ’,γ”相析出強化型高Ni鋼において、粒度調整
後、1060℃〜1150℃で溶体化処理を施し、その
後、10〜30%の冷間加工、700℃〜900℃で時
効処理を施した高Ni鋼。
(4) In the γ ', γ "phase precipitation strengthened high Ni steel described in any one of items 1 to 3, after grain size adjustment, solution treatment is performed at 1060 ° C to 1150 ° C, and then 10 to 30. % Cold-worked, high Ni steel aged at 700 ° C to 900 ° C.

【0011】以下、本発明について詳細に説明する。な
お、本明細書中にて使用される「γ’,γ”」とは、
γ’及び/またはγ”の意味であり、γ’はNi3
l,Ni3 Ti、γ”はNi3 Nbを成分とするNiと
の金属間化合物で、0.01μm以下の微細な析出物を
いう。
The present invention will be described in detail below. In addition, "γ ', γ""used in the present specification means
means γ'and / or γ ", and γ'is Ni 3 A
l, Ni 3 Ti, γ ″ is an intermetallic compound with Ni containing Ni 3 Nb as a component, and means a fine precipitate of 0.01 μm or less.

【0012】本発明材料は、Fe−Cr−Ni系鋼を主
体とし、固溶強化元素としてMo、Wを添加し、さら
に、γ’,γ”の析出強化元素としてTi、Al、Nb
の複合添加をし、このTi、Al、Nbの複合添加にお
いては特にNbを多く添加する成分を有することを特徴
としている。
The material of the present invention is mainly composed of Fe-Cr-Ni system steel, to which Mo and W are added as solid solution strengthening elements, and Ti, Al and Nb as precipitation strengthening elements of γ ', γ ".
The compound addition of Ti, Al, and Nb is characterized by having a component that particularly adds a large amount of Nb.

【0013】Siは、脱酸剤として添加されるが、0.
5%を越えると照射中に有害な金属間化合物が析出しや
すくなり、脆化をもたらすので、0.5%以下とする。
Although Si is added as a deoxidizer, Si.
If it exceeds 5%, harmful intermetallic compounds tend to precipitate during irradiation, causing embrittlement, so the content is made 0.5% or less.

【0014】Mnは、熱間加工性を改善し、組織の安定
化に有効であるが、1.0%を越えると硬化相を形成
し、靭性、加工性を損うので、1.0%以下とする。
Mn improves hot workability and is effective in stabilizing the structure, but if it exceeds 1.0%, a hardened phase is formed and toughness and workability are impaired. Below.

【0015】Crは、耐ナトリウム腐食性、脱炭抵抗性
を向上させるために不可欠な成分であり、そのためには
13%以上が必要である。しかし、18%を越えると、
組織を不安定にし、有害な金属間化合物が析出しやすく
なる。とくに、中性子照射下では相不安定性による粒界
析出脆化が起きやすい。従って、Cr量は13%〜18
%の範囲とする。
Cr is an essential component for improving sodium corrosion resistance and decarburization resistance, and 13% or more is required for that purpose. However, if it exceeds 18%,
The structure becomes unstable and harmful intermetallic compounds are easily deposited. In particular, grain boundary precipitation embrittlement due to phase instability easily occurs under neutron irradiation. Therefore, the Cr content is 13% to 18
The range is%.

【0016】Niは、オーステナイト安定化元素である
と共に、耐スエリング性を向上させる上で重要な元素で
あり、そのためには最低30%必要である。しかし、5
0%を越えると、照射による残留放射能が著しく高くな
り、廃棄物の保管及び再処理上問題となる。また、耐ナ
トリウム腐食特性も低下する。更に、NiはHe脆化の
原因ともなる(Niは中性子と反応してHeを生じる)
ので、Ni量は30〜50%とする。
Ni is an austenite stabilizing element and an important element for improving the swelling resistance, and at least 30% is required for that purpose. But 5
If it exceeds 0%, the residual radioactivity due to irradiation becomes extremely high, which poses a problem in storage and reprocessing of waste. In addition, the sodium corrosion resistance is also reduced. Further, Ni also causes He embrittlement (Ni reacts with neutrons to generate He).
Therefore, the Ni content is 30 to 50%.

【0017】MoとWは、固溶強化元素として重要であ
り、総量で2.0%以上添加する必要がある。しかし、
6.0%以上添加すると中性子吸収断面積が大きくな
り、増殖性の問題となる。また、μ相(Fe7 (Mo,
W)6 )が生じ、延性を低下させる。従って、(Mo+
W)量は、2.0〜6.0%とする。
Mo and W are important as solid solution strengthening elements and must be added in a total amount of 2.0% or more. But,
If it is added in an amount of 6.0% or more, the neutron absorption cross section becomes large, which causes a problem of proliferation. In addition, μ phase (Fe 7 (Mo,
W) 6 ) occurs and reduces ductility. Therefore, (Mo +
The amount of W) is 2.0 to 6.0%.

【0018】TiとAlとNbは、金属間化合物
(γ’,γ”)を形成し、析出強化元素として重要とな
る。
Ti, Al and Nb form an intermetallic compound (γ ', γ ") and are important as precipitation strengthening elements.

【0019】即ち、市販されている類似の鋼においても
γ’,γ”にて強度を高めることはよく行われているこ
とであるが、本発明に係る高Ni鋼の場合には使用温度
が700℃でかつ中性子照射下での延性が必要とされる
ことから、γ’,γ”量を10vol.%以下に制限す
る必要があると共に、少なくとも固溶化温度(γ’,
γ”が溶ける温度)は800℃以上とする必要がある。
このような固溶化温度を得るためにはTi、Al、Nb
のいずれか1つの成分を多く含むのが有効であるという
ことが実験で確かめられている。即ち、固溶化温度と関
係するγ,γ+γ’、γ”相境界温度の高い試料は、T
i、Al、Nbのどれか1つの成分(mol量)が高く
なっているのである。しかしながら、Ti量の多い試料
は引張延性に劣り、Al量の多い試料はクリープ強度に
劣るということが分かった。一方、Nb量の多い試料に
はこのような不都合はなく、Nb量の多い試料はクリー
プ強度、引張延性ともに優れた特性を示す。本発明で
は、十分な延性確保のためにγ’,γ”量を10vo
l.%以下とする必要にも鑑みて、これらの量は、Al
=0.05〜1.0%、Ti=0.05〜0.6%、N
b=2〜5%とすることにしている。
That is, it is common to increase the strength by γ ', γ "even in the similar steels on the market, but in the case of the high Ni steel according to the present invention, the operating temperature is Since the ductility at 700 ° C. and under neutron irradiation is required, the amount of γ ′, γ ″ is set to 10 vol. % Or less, and at least the solution temperature (γ ',
The temperature at which γ ″ melts) must be 800 ° C. or higher.
To obtain such solution temperature, Ti, Al, Nb
It has been confirmed by experiments that it is effective to contain a large amount of any one of the components. That is, a sample having a high γ, γ + γ ′, γ ″ phase boundary temperature related to the solution temperature is T
The component (mol amount) of any one of i, Al, and Nb is high. However, it was found that the sample having a large amount of Ti was inferior in tensile ductility and the sample having a large amount of Al was inferior in creep strength. On the other hand, the sample with a large amount of Nb does not have such inconvenience, and the sample with a large amount of Nb exhibits excellent characteristics in both creep strength and tensile ductility. In the present invention, in order to secure sufficient ductility, the amounts of γ ′ and γ ″ are set to 10 vo
l. %, In consideration of the need to maintain the content of Al at most,
= 0.05-1.0%, Ti = 0.05-0.6%, N
b = 2 to 5%.

【0020】γ’,γ”の析出上限温度が1050℃程
度なので、溶体化温度は最低1060℃とする。γ’,
γ”の量が増加すれば析出上限温度は上昇するが、熱処
理温度を高くし過ぎると結晶粒が大きくなり、超音波探
傷検査ができなくなるので上限を1150℃とする。次
にγ’,γ”を微細析出させるために冷間加工により転
位を導入し、転位上に析出させる必要がある。転位上に
析出させるには最低10%の冷間加工が必要である。3
0%を越えると導入した転位によりクリープ強度が低下
するのでこれを上限とする。時効温度については、高速
炉の使用温度が700℃程度なので、それ以上で析出さ
せることが望ましい。従って、時効温度は700℃を下
限とする。また、900℃を越えると析出するγ’,
γ”が粗大化するので、上限を900℃とする。
Since the precipitation upper limit temperature of γ ', γ "is about 1050 ° C, the solutionizing temperature is at least 1060 ° C.
If the amount of γ ″ increases, the upper limit temperature of precipitation rises, but if the heat treatment temperature is too high, the crystal grains become large and ultrasonic flaw inspection cannot be performed, so the upper limit is set to 1150 ° C. Next, γ ′, γ It is necessary to introduce dislocations by cold working and precipitate them on the dislocations in order to finely precipitate ". A minimum of 10% cold work is required to precipitate on dislocations. Three
If it exceeds 0%, the creep strength decreases due to the introduced dislocations, so this is made the upper limit. Regarding the aging temperature, since the operating temperature of the fast reactor is about 700 ° C, it is desirable to precipitate it at a temperature higher than that. Therefore, the lower limit of the aging temperature is 700 ° C. In addition, γ'precipitated above 900 ° C,
Since γ ″ becomes coarse, the upper limit is set to 900 ° C.

【0021】[0021]

【実施例】真空溶解、均質化熱処理(1200℃×20
h)、熱間鍛造、熱間圧延、中間焼鈍(1100℃×3
0min WQ)により、厚さ20mmの板を作り、5
0%冷間圧延、溶体化処理(1040〜1080×30
min WQ)により、結晶粒度を調整し、8tの板材
を作る。最後に、20%の冷間加工、750℃×8hの
時効処理により供試材を仕上げる。供試材の成分を表1
に示す。
[Example] Vacuum melting, homogenizing heat treatment (1200 ° C x 20
h), hot forging, hot rolling, intermediate annealing (1100 ° C x 3
0min WQ) to make a plate with a thickness of 20mm, and
0% cold rolling, solution treatment (1040 to 1080 × 30
min WQ) to adjust the grain size and make a plate material of 8t. Finally, the test material is finished by 20% cold working and aging treatment at 750 ° C. for 8 hours. Table 1 shows the composition of the test material
Shown in.

【0022】[0022]

【表1】 この表1に示される各供試材のクリープ破断試験結果を
図1に示す。この図1に示される結果から、本実施例に
係る供試材は、Ti、Nbを多量に添加した材料は実証
炉被覆管候補材であるPNC1520を上回る優れたク
リープ強度を示すということが分かる。
[Table 1] The results of the creep rupture test of each of the test materials shown in Table 1 are shown in FIG. From the results shown in FIG. 1, it can be seen that the test material according to the present example shows that the material in which a large amount of Ti and Nb are added exhibits an excellent creep strength exceeding that of PNC1520 which is the candidate material for the cladding tube of the demonstration reactor. .

【0023】図2には引張試験における伸びを示す。こ
の図2に示される結果より、Tiを多く添加した材料
は、優れたクリープ強度を示す半面、引張、延性に劣る
ことがわかる。発明鋼であるNbを多く添加した材料
は、引張、延性共に良好であるということがわかる。
FIG. 2 shows the elongation in the tensile test. From the results shown in FIG. 2, it can be seen that the material to which a large amount of Ti has been added exhibits poor creep strength, but is poor in tensile strength and ductility. It can be seen that the material of the invention steel containing a large amount of Nb has good tensile properties and ductility.

【0024】表1に示されるNo.7の試料について
は、特に熱処理の影響についても調べた。トリアーク炉
で60gのボタンインゴットを溶解し、均質化処理(1
200℃×24h)、熱間圧延(1200℃)で4tの
板とする。中間熱処理(1100℃×30min W
Q)、20%冷間圧延、溶体化処理(1080℃×4
h)により試験片を作製した。次に、以下の4つの熱処
理とγ’,γ”の析出状況を調べた。
No. 1 shown in Table 1 For the sample of No. 7, the effect of heat treatment was also examined. 60g button ingot was melted in a tri-arc furnace and homogenized (1
A plate of 4 t is formed by hot rolling (1200 ° C.) at 200 ° C. for 24 hours. Intermediate heat treatment (1100 ℃ × 30min W
Q), 20% cold rolling, solution heat treatment (1080 ° C x 4
A test piece was prepared according to h). Next, the following four heat treatments and the precipitation state of γ ′ and γ ″ were investigated.

【0025】 (A)1080℃×1h→20%CW→900℃×1h→750℃×8h (B)1080℃×1h→900℃×1h→750℃×8h (C)1080℃×1h→20%CW→750℃×8h (D)1080℃×1h→750℃×8h 析出状況を電子顕微鏡観察により調べた結果を表2に示
す。
(A) 1080 ° C. × 1 h → 20% CW → 900 ° C. × 1 h → 750 ° C. × 8 h (B) 1080 ° C. × 1 h → 900 ° C. × 1 h → 750 ° C. × 8 h (C) 1080 ° C. × 1 h → 20 % CW → 750 ° C. × 8 h (D) 1080 ° C. × 1 h → 750 ° C. × 8 h Table 2 shows the results of examination of the precipitation state by electron microscope observation.

【0026】[0026]

【表2】 この表2より、(C)の熱処理が最も有効であるこいう
ことが分かる。
[Table 2] It can be seen from Table 2 that the heat treatment of (C) is most effective.

【0027】[0027]

【発明の効果】以上のように、本発明によれば耐スエリ
ング性と高温クリープ強度、照射下での相安定性につい
てバランスのとれた高Ni鋼が提供できる。即ち、本発
明によれば、耐照射特性と高温強度、延性に優れた
γ’,γ”相析出強化型高Ni鋼を提供することができ
る。このことから、本発明によれば、原子炉(特に高速
増殖炉部材)の構造部材、特に燃料被覆管のような70
0℃程度の高温で、しかも高い応力下で使用される構造
部材の長寿命化を達成することができる。
As described above, according to the present invention, it is possible to provide a high Ni steel having a well-balanced swelling resistance, high temperature creep strength and phase stability under irradiation. That is, according to the present invention, it is possible to provide a γ ′, γ ”phase precipitation strengthened high Ni steel excellent in irradiation resistance, high temperature strength and ductility. 70, such as structural members (especially fast breeder reactor members), especially fuel cladding
It is possible to achieve a long service life of a structural member used at a high temperature of about 0 ° C. and under a high stress.

【図面の簡単な説明】[Brief description of drawings]

【図1】試作材(供試材)について700℃におけるク
リープ破断試験の結果を示した図である。
FIG. 1 is a diagram showing the results of a creep rupture test at 700 ° C. for a trial material (test material).

【図2】試作材(供試材)の引張伸びを比較した結果を
示した図である。
FIG. 2 is a diagram showing a result of comparison of tensile elongations of trial materials (test materials).

───────────────────────────────────────────────────── フロントページの続き (72)発明者 鵜飼 重治 茨城県東茨城郡大洗町成田町4002番地 動 力炉・核燃料開発事業団 大洗工学センタ ー内 (72)発明者 鹿倉 栄 茨城県東茨城郡大洗町成田町4002番地 動 力炉・核燃料開発事業団 大洗工学センタ ー内 (72)発明者 原田 誠 兵庫県神戸市西区学園西町5−8−1, 527−205 (72)発明者 西田 俊夫 茨城県東茨城郡大洗町成田町4002番地 動 力炉・核燃料開発事業団 大洗工学センタ ー内 ─────────────────────────────────────────────────── ─── Continuation of the front page (72) Inventor Shigeharu Ukai 4002 Narita-cho, Oarai-cho, Higashi-Ibaraki-gun, Ibaraki-ken Within the Oarai Engineering Center, Power Reactor and Nuclear Fuel Development Corp. Oarai-cho Narita-cho 4002 Power Reactor and Nuclear Fuel Development Corporation Oarai Engineering Center (72) Inventor Makoto Harada 5-8-1, 527-205 Gakuen Nishimachi, Nishi-ku, Kobe-shi, Hyogo (72) Inventor Toshio Nishida Ibaraki 4002 Narita-cho, Oarai-cho, Higashi-Ibaraki-gun, Japan Oarai Engineering Center, Reactor and Nuclear Fuel Development Corporation

Claims (4)

【特許請求の範囲】[Claims] 【請求項1】 重量%でSi:0.5%以下、Mn:
1.0%以下、Cr:13〜18%、Ni:30〜50
%、Mo+W=2.0〜6.0%、Al=0.05〜
1.0%、Ti=0.05〜0.6%、Nb=2〜5
%、残部がFe及び不可避不純物からなることを特徴と
するγ’,γ”相析出強化型高Ni鋼。
1. Si: 0.5% or less by weight%, Mn:
1.0% or less, Cr: 13-18%, Ni: 30-50
%, Mo + W = 2.0 to 6.0%, Al = 0.05 to
1.0%, Ti = 0.05 to 0.6%, Nb = 2 to 5
%, The balance being Fe and unavoidable impurities, and a γ ′, γ ″ phase precipitation strengthening high Ni steel.
【請求項2】 請求項1記載の高Ni鋼において、0.
08%以下のPが添加されていることを特徴とする高N
i鋼。
2. The high Ni steel according to claim 1, wherein
High N, characterized by the addition of 08% or less P
i steel.
【請求項3】 請求項1または2記載の高Ni鋼におい
て、0.01%以下のBが添加されていることを特徴と
する高Ni鋼。
3. The high Ni steel according to claim 1 or 2, wherein B is added in an amount of 0.01% or less.
【請求項4】 請求項1乃至3いずれか記載のγ’,
γ”相析出強化型高Ni鋼において粒度調整後、104
0℃〜1150℃で溶体化処理を施し、その後、10〜
30%の冷間加工、700℃〜900℃で時効処理を施
した高Ni鋼。
4. The γ ′ according to any one of claims 1 to 3,
After adjusting the grain size in γ "phase precipitation strengthened high Ni steel, 104
Solution treatment is performed at 0 ° C to 1150 ° C, and then 10
High Ni steel that has been cold worked at 30% and aged at 700 ° C to 900 ° C.
JP6226307A 1994-09-21 1994-09-21 γ ', γ "phase precipitation strengthened high Ni steel Pending JPH0892700A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP6226307A JPH0892700A (en) 1994-09-21 1994-09-21 γ ', γ "phase precipitation strengthened high Ni steel

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP6226307A JPH0892700A (en) 1994-09-21 1994-09-21 γ ', γ "phase precipitation strengthened high Ni steel

Publications (1)

Publication Number Publication Date
JPH0892700A true JPH0892700A (en) 1996-04-09

Family

ID=16843160

Family Applications (1)

Application Number Title Priority Date Filing Date
JP6226307A Pending JPH0892700A (en) 1994-09-21 1994-09-21 γ ', γ "phase precipitation strengthened high Ni steel

Country Status (1)

Country Link
JP (1) JPH0892700A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2002241841A (en) * 2001-01-24 2002-08-28 Imphy Ugine Precision Method for producing strip made from iron-nickel alloy
CN115558859A (en) * 2022-10-10 2023-01-03 江苏图南合金股份有限公司 High-hardness alloy for high-temperature extrusion die, forging and production method of forging

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2002241841A (en) * 2001-01-24 2002-08-28 Imphy Ugine Precision Method for producing strip made from iron-nickel alloy
CN115558859A (en) * 2022-10-10 2023-01-03 江苏图南合金股份有限公司 High-hardness alloy for high-temperature extrusion die, forging and production method of forging

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