JPH0456750A - Austenitic iron base alloy - Google Patents
Austenitic iron base alloyInfo
- Publication number
- JPH0456750A JPH0456750A JP16673390A JP16673390A JPH0456750A JP H0456750 A JPH0456750 A JP H0456750A JP 16673390 A JP16673390 A JP 16673390A JP 16673390 A JP16673390 A JP 16673390A JP H0456750 A JPH0456750 A JP H0456750A
- Authority
- JP
- Japan
- Prior art keywords
- less
- stainless steel
- austenitic
- austenitic stainless
- equipment
- 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
- 229910045601 alloy Inorganic materials 0.000 title claims abstract description 11
- 239000000956 alloy Substances 0.000 title claims abstract description 11
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 title claims description 26
- 229910052742 iron Inorganic materials 0.000 title claims description 12
- 229910052746 lanthanum Inorganic materials 0.000 claims abstract description 16
- 229910052684 Cerium Inorganic materials 0.000 claims abstract description 15
- 229910000963 austenitic stainless steel Inorganic materials 0.000 claims abstract description 13
- 229910052748 manganese Inorganic materials 0.000 claims abstract description 5
- 229910052710 silicon Inorganic materials 0.000 claims abstract description 5
- 229910052799 carbon Inorganic materials 0.000 claims abstract description 4
- 229910052804 chromium Inorganic materials 0.000 claims abstract description 4
- 229910052759 nickel Inorganic materials 0.000 claims abstract description 4
- 229910052698 phosphorus Inorganic materials 0.000 claims abstract description 4
- 229910052750 molybdenum Inorganic materials 0.000 claims abstract description 3
- 229910052717 sulfur Inorganic materials 0.000 claims abstract description 3
- PXHVJJICTQNCMI-UHFFFAOYSA-N Nickel Chemical compound [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 claims description 6
- GWXLDORMOJMVQZ-UHFFFAOYSA-N cerium Chemical compound [Ce] GWXLDORMOJMVQZ-UHFFFAOYSA-N 0.000 claims description 5
- FZLIPJUXYLNCLC-UHFFFAOYSA-N lanthanum atom Chemical compound [La] FZLIPJUXYLNCLC-UHFFFAOYSA-N 0.000 claims description 5
- 239000011572 manganese Substances 0.000 claims description 4
- VYZAMTAEIAYCRO-UHFFFAOYSA-N Chromium Chemical compound [Cr] VYZAMTAEIAYCRO-UHFFFAOYSA-N 0.000 claims description 3
- OAICVXFJPJFONN-UHFFFAOYSA-N Phosphorus Chemical compound [P] OAICVXFJPJFONN-UHFFFAOYSA-N 0.000 claims description 3
- 239000011651 chromium Substances 0.000 claims description 3
- 239000011574 phosphorus Substances 0.000 claims description 3
- 239000010703 silicon Substances 0.000 claims description 3
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 claims description 2
- PWHULOQIROXLJO-UHFFFAOYSA-N Manganese Chemical compound [Mn] PWHULOQIROXLJO-UHFFFAOYSA-N 0.000 claims description 2
- ZOKXTWBITQBERF-UHFFFAOYSA-N Molybdenum Chemical compound [Mo] ZOKXTWBITQBERF-UHFFFAOYSA-N 0.000 claims description 2
- NINIDFKCEFEMDL-UHFFFAOYSA-N Sulfur Chemical compound [S] NINIDFKCEFEMDL-UHFFFAOYSA-N 0.000 claims description 2
- 239000011733 molybdenum Substances 0.000 claims description 2
- 239000011593 sulfur Substances 0.000 claims description 2
- 230000007797 corrosion Effects 0.000 abstract description 18
- 238000005260 corrosion Methods 0.000 abstract description 18
- 238000005336 cracking Methods 0.000 abstract description 8
- 229910000640 Fe alloy Inorganic materials 0.000 abstract 1
- 238000004519 manufacturing process Methods 0.000 abstract 1
- 239000012535 impurity Substances 0.000 description 7
- 239000000463 material Substances 0.000 description 7
- 230000000694 effects Effects 0.000 description 4
- 150000001875 compounds Chemical class 0.000 description 3
- 238000005204 segregation Methods 0.000 description 3
- 206010070834 Sensitisation Diseases 0.000 description 2
- 229910000831 Steel Inorganic materials 0.000 description 2
- 229910001566 austenite Inorganic materials 0.000 description 2
- 230000015572 biosynthetic process Effects 0.000 description 2
- 238000009835 boiling Methods 0.000 description 2
- 230000008313 sensitization Effects 0.000 description 2
- 229910001220 stainless steel Inorganic materials 0.000 description 2
- 239000010959 steel Substances 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- 229910018062 Ni-M Inorganic materials 0.000 description 1
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 description 1
- 101150062705 Wipf3 gene Proteins 0.000 description 1
- 230000015556 catabolic process Effects 0.000 description 1
- JOPOVCBBYLSVDA-UHFFFAOYSA-N chromium(6+) Chemical compound [Cr+6] JOPOVCBBYLSVDA-UHFFFAOYSA-N 0.000 description 1
- 239000000470 constituent Substances 0.000 description 1
- 230000007423 decrease Effects 0.000 description 1
- 230000002950 deficient Effects 0.000 description 1
- 238000006731 degradation reaction Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000006870 function Effects 0.000 description 1
- 230000003340 mental effect Effects 0.000 description 1
- 150000001247 metal acetylides Chemical class 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 229910017604 nitric acid Inorganic materials 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 238000003466 welding Methods 0.000 description 1
Landscapes
- Heat Treatment Of Articles (AREA)
Abstract
Description
【発明の詳細な説明】
［産業上の利用分野］
本発明はオーステナイト鉄基合金に係り、特に原子炉炉
内機器に好適な耐食性に優れたオーステナイト鉄基合金
に関する。DETAILED DESCRIPTION OF THE INVENTION [Industrial Application Field] The present invention relates to an austenitic iron-based alloy, and particularly to an austenitic iron-based alloy with excellent corrosion resistance suitable for equipment in a nuclear reactor.
［従来の技術］
オーステナイト系ステンレス鋼製の制御棒、炉内計装管
等の原子炉炉内機器は、常に高温純水という環境に置か
れるうえに、他の原子炉構成材料に比べて比較的高い中
性子照射を受けている。−方、高温純水中でオーステナ
イト系ステンレス鋼は、粒界応力腐食割れ（Ｉａｓｃｃ
）を起こすことがある。ＩＧＳＣＣの主たる材料側の因
子は、溶接などの熱サイクルによる粒界炭化物の形成と
それに伴なう粒界近傍におけるクロム欠乏層の形成、す
なわち、溶接鋭敏化である。しかしながら、鋭敏化が全
く起こっていない溶体化オーステナイト系ステンレス鋼
においても、照射を受けた場合、非照射材に比べて高い
粒界腐食割れ感受性を示すという報告も出されている。[Conventional technology] In-core reactor equipment such as control rods and in-core instrumentation tubes made of austenitic stainless steel are constantly placed in an environment of high-temperature pure water, and compared to other reactor constituent materials, Receives high neutron irradiation. On the other hand, austenitic stainless steel undergoes intergranular stress corrosion cracking (Iascc) in high-temperature pure water.
) may occur. The main material-related factors in IGSCC are the formation of grain boundary carbides due to thermal cycles such as welding and the accompanying formation of a chromium-deficient layer near the grain boundaries, that is, weld sensitization. However, it has been reported that even solution-treated austenitic stainless steel, which has not undergone any sensitization, exhibits higher intergranular corrosion cracking susceptibility when irradiated than non-irradiated material.
照射による材料への影響としては、照射によって引き起
こされる照射誘起偏析により、Ｓｉ（ケイ素）およびＰ
（リン）等が濃縮して粒界の耐食性が低下することが考
えられる。The effects of irradiation on materials include Si (silicon) and P due to irradiation-induced segregation caused by irradiation.
It is thought that corrosion resistance of grain boundaries decreases due to concentration of (phosphorus) and the like.
高純度オーステナイト系ステンレス鋼は、上記因子に着
目し、不純物元素量を限定することにより高照射を受け
た場合でも耐粒界腐食割れ性の優れた性能を有すること
を目的として開発されたものである。なお、この種の技
術に関する文献として、例えば、「オーステナイト鋼の
粒界腐食」（Ｊ、Ｓ、Ａｒｍ１ｊｏ、Ｃｏｒｒｏｓｉｏ
ｎ、ｖｏｌ、２４、 ｐ、２４（１９６８）：１：ｎｔ
ｅ−ｒｇｒａｎｕＬａｒ Ｃｏｒｒｏｓｉｏｎ ｏｆ
Ｎｏｎ５ｅｎｓｉｔｉｚｅｄ Ａｕ５ｔｅｎｉ−ｔｉｅ
５ｔｅｅｌｓ）、あるいはｒＢｌＩＲおよびＰＷＲ炉
心におけるオーステナイト系ステンレス鋼およびＮｉ基
合金の変形特性」（Ｆ、Ｇａｒａｚａｒｏｌｌｉ ｅｔ
ａｌ、、Ｐｒｏｃ＋Ｉｎｔ、Ｓｙｍｐ、Ｅｎｖｉｒｏ
ｎｍｅｎｔａｌ Ｄｅｇｒａｄａｔｉｏｎ ｏｆ Ｍａ
ｔｅｒｉａｌｓｉｎ Ｎｕｃｌｅａｒ Ｓｙｓｔｅ
ｍ−１ｉ１ａｔｅｒ Ｒｅａｃｔｏｒｓ、阿ｏｎｔｅ
ｒｙ、Ｃａｌ。High-purity austenitic stainless steel was developed with a focus on the above factors, with the aim of providing excellent intergranular corrosion cracking resistance even when subjected to high irradiation by limiting the amount of impurity elements. be. In addition, as a literature related to this type of technology, for example, "Intergranular Corrosion of Austenitic Steel" (J, S., Arm1jo, Corrosio
n, vol, 24, p, 24 (1968):1:nt
e-rgranuLar Corrosion of
Non5ensitized Au5teni-tie
"Deformation Properties of Austenitic Stainless Steels and Ni-Based Alloys in rBlIR and PWR Cores" (F, Garazzarolli et al.
al,, Proc+Int, Symp, Enviro
Mental Degradation of Ma
terialsin Nuclear System
m-1i1ater Reactors, Aonte
ry, Cal.
Ｌｌ、Ｓ、Ａ、Ｓｅｐ、ｐ、４４２（１９８３）：Ｄｅ
ｆｏｒｍａｂｉｌｉｔｙ ｏｆ Ａｕ５ｔｅｎｉｔｉｃ
５ｔａｉｎｌｅｓｓ ５ｔｅｅｌ ａｎｄ Ｎ１−ｂ
ａｓｅ Ａ１１ａｙ ｉｎ ｔｈｅｃｏｒｅ ｏｆ ａ
Ｂｏｉｌｉｎｇ ａｎｄ ａ Ｐｒｅｓｓｕｒｉｚｅ
ｄ ＷａｔｅｒＲｅａｃｔｏｒ）が挙げられる。Ll, S, A, Sep, p, 442 (1983): De
Formability of Au5tenitic
5stainless 5teel and N1-b
ase A11ay in the core of a
Boiling and a Pressurize
dWaterReactor).
［発明が解決しようとする課題］
しかしながら、上記の高純度オーステナイト系ステンレ
ス鋼は、通常純度のステンレス鋼（以下通常純度材とい
う）に比べて照射脆化の程度が大きく、機械的特性上問
題があることが明らかになった。この原因としては、照
射によって生成する転位ループの生成核として作用する
不純物元素が高純度化することにより少なくなり、照射
脆化のもとである転位ループ形態が通常純度材と異なる
ため照射脆化しやすくなることが考えられる。[Problem to be solved by the invention] However, the above-mentioned high-purity austenitic stainless steel has a greater degree of irradiation embrittlement than normal-purity stainless steel (hereinafter referred to as normal-purity material), and has problems in terms of mechanical properties. One thing became clear. The reason for this is that impurity elements that act as nuclei for dislocation loops generated by irradiation are reduced due to high purity, and the form of dislocation loops that cause irradiation embrittlement is different from that of ordinary pure materials, which causes irradiation embrittlement. It is possible that it will become easier.
本発明は上記の状況に鑑みなされたもので、通常純度材
において、特に高純度化することなく、不純物元素の粒
界偏析を阻止することにより耐粒界腐食割れ性を向上で
きるオーステナイト鉄基台金を提供することを目的とし
たものである。The present invention was made in view of the above circumstances, and is an austenitic iron base that can improve intergranular corrosion cracking resistance by preventing grain boundary segregation of impurity elements in normally pure materials without particularly increasing the purity. The purpose is to provide money.
［課題を解決するための手段］
上記課題を解決するための本発明に係るオーステナイト
鉄基合金の構成は、ニッケル１０．０〜１４．０ｗｔ％
、クロム１６．０〜１８．０ｗｔ％、モリブデン２．０
〜３゜０ｗｔ％、炭素０゜０３ｗｔ％以下、マンガン２
．０ｗｔ％以下、リン０．０４ｗｔ％以下、硫黄０．０
３ｗｔ％以下、ケイ素１．０ｗｔ％以下、残部が主とし
て鉄からなるオーステナイト系ステンレス鋼に、ランタ
ンまたはセリウムを０．５〜１．０ｗｔ％となるように
含有させるようにしたことである。[Means for Solving the Problems] The composition of the austenitic iron-based alloy according to the present invention for solving the above problems is as follows: 10.0 to 14.0 wt% nickel
, chromium 16.0-18.0wt%, molybdenum 2.0
~3゜0wt%, carbon 0゜03wt% or less, manganese 2
．． 0wt% or less, phosphorus 0.04wt% or less, sulfur 0.0
The austenitic stainless steel contains 0.5 to 1.0 wt% of lanthanum or cerium to an austenitic stainless steel consisting of 3 wt% or less, 1.0 wt% or less of silicon, and the remainder mainly iron.
［作用］
本発明は、Ｎｉ １０．０〜１４．０ｗｔ％、Ｃｒ１６
．Ｏ〜１８．０ｗｔ％、Ｍｏ２．０〜３．０ｗｔ％、Ｃ
ｏ、０３ｗｔ％以下、Ｍｎ２．０ｗｔ％以下、Ｐｏ、０
４ｗｔ％以下Ｓｏ、０３ｗｔ％以下、Ｓｉ１．０ｗｔ％
以下、残部が主として鉄からなる５ＵＳ３１６Ｌオース
テナイト系ステンレス鋼に、不純物元素と化合物を形成
しやすいＬａ（ランタン）またはＣｅ（セリウム）を含
有させたことにより不純物元素を粒内に固定することが
できる。その結果、高純度化することなく不純物元素の
粒界偏析を防止することができ、高純度化による照射脆
化の問題も解決することができる。[Function] The present invention has Ni 10.0 to 14.0 wt%, Cr16
．． O~18.0wt%, Mo2.0~3.0wt%, C
o, 03 wt% or less, Mn 2.0 wt% or less, Po, 0
4wt% or less So, 03wt% or less, Si1.0wt%
Hereinafter, impurity elements can be fixed within the grains by incorporating La (lanthanum) or Ce (cerium), which easily form compounds with impurity elements, into 5US316L austenitic stainless steel, the remainder of which is mainly iron. As a result, grain boundary segregation of impurity elements can be prevented without increasing the purity, and the problem of irradiation embrittlement due to the increase in purity can also be solved.
ただし、ＬａおよびＣｅを多量に添加するとオーステナ
イト相が不安定になり、Ｆｅ系化合物を形成しやすくな
るのでＬａおよびＣｅの添加量は１．０ｗｔ％以下が好
ましい。また、不純物元素と化合物を形成させるため少
なくとも０．５ｗｔ％以上添加する必要がある。However, if large amounts of La and Ce are added, the austenite phase becomes unstable and Fe-based compounds are likely to be formed, so the amounts of La and Ce added are preferably 1.0 wt% or less. Further, in order to form a compound with an impurity element, it is necessary to add at least 0.5 wt% or more.
［実施例］ 本発明の実施例を図面を参照して説明する。[Example] Embodiments of the present invention will be described with reference to the drawings.
まず、ｗｔ％で、Ｎｉ １０．Ｏ〜１４．０％、Ｃｒ１
６．Ｏ〜１８．０％、Ｍｏ２．０〜３．０％以下、Ｃｏ
、０３％以下、Ｍｎ２．０％以下。First, in wt%, Ni 10. O~14.0%, Cr1
6. O~18.0%, Mo2.0~3.0% or less, Co
, 03% or less, Mn 2.0% or less.
Ｐｏ、０４％以下、Ｓｏ、０３％以下Ｓｉ１．０％以下
、残部が主としてＦｅからなるオーステナイト系ステン
レス鋼に、ＬａまたはＣｅを種々の濃度（０、１〜２
、 Ｏｗ ｔ％）で含有させて、Ｆｅ−Ｃｒ−Ｎｉ−Ｍ
ｏ−ＬａおよびＦ ｅ −Ｃｒ−Ｎ ｉ −Ｍ ｏ −
Ｃｅの２系統のオーステナイト鉄基合金を製造し、粒界
腐食試験を実施して、夫々のＬａおよびＣｅ添加の効果
を調べた。Austenitic stainless steel consisting of Po, 0.4% or less, So, 0.3% or less, Si 1.0% or less, and the remainder mainly Fe, is coated with La or Ce at various concentrations (0, 1 to 2
, Ow t%), Fe-Cr-Ni-M
o-La and Fe-Cr-Ni-Mo-
Two types of austenitic iron-based alloys containing Ce were manufactured, and intergranular corrosion tests were conducted to investigate the effects of adding La and Ce, respectively.
粒界腐食試験は６価クロムを含む５規定沸騰硝゛酸液に
各被試験鋼を６時間浸漬して行った。その結果を図面に
示す。図面において横軸はＬａまたはＣｅ濃度を表し、
縦軸は粒界腐食感受性（割れ長さの比）を表す。この図
に示すようにＬａまたはＣｅの濃度を０．５ｗｔ％以上
にすると耐粒界腐食割れ性が著しく向上することがわか
る。The intergranular corrosion test was conducted by immersing each steel to be tested in a 5N boiling nitric acid solution containing hexavalent chromium for 6 hours. The results are shown in the drawing. In the drawing, the horizontal axis represents La or Ce concentration,
The vertical axis represents intergranular corrosion susceptibility (crack length ratio). As shown in this figure, it can be seen that when the concentration of La or Ce is 0.5 wt% or more, the intergranular corrosion cracking resistance is significantly improved.
また、例えば５ＵＳ３１６Ｌオーステナイト系ステンレ
ス鋼中へのＬａまたはＣｅ元素の添加はオーステナイト
相の安定性等から、最大１．０ｗｔ％と推定されるので
、本実施例におけるＬａまたはＣｅの添加量は、０．５
〜１．０ｗｔ％が好適である。Furthermore, for example, the addition of La or Ce elements to 5US316L austenitic stainless steel is estimated to be at most 1.0 wt% from the stability of the austenite phase, etc., so the amount of La or Ce added in this example is 0. .5
~1.0 wt% is suitable.
本実施例の効果は、耐食性および耐脆性破壊にすぐれた
原子炉炉内機器用のオーステナイト鉄基合金が得られた
ことである。The effect of this example is that an austenitic iron-based alloy for internal equipment in a nuclear reactor with excellent corrosion resistance and brittle fracture resistance was obtained.
［発明の効果コ
以上説明したように、本発明のオーステナイト鉄基合金
は、所定量のランタンまたはセリウムを含有したことに
よって、中性子照射を受けてもＩＧＳＣＣの発生しにく
い、耐粒界腐食割れ性に優れた原子炉炉内機器用の材料
を提供することがで腐食試験におけるランタンまたはセ
リウム濃度（ｗｔ％）と粒界腐食感受性の関係図である
。[Effects of the Invention] As explained above, the austenitic iron-based alloy of the present invention, by containing a predetermined amount of lanthanum or cerium, has excellent intergranular corrosion cracking resistance and is resistant to IGSCC even when subjected to neutron irradiation. This is a diagram showing the relationship between lanthanum or cerium concentration (wt%) and intergranular corrosion susceptibility in corrosion tests.
〈符号の説明〉<Explanation of symbols>
Claims (1)
０〜１８．０ｗｔ％、モリブデン２．０〜３．０ｗｔ％
、炭素０．０３ｗｔ％以下、マンガン２．０ｗｔ％以下
、リン０．０４ｗｔ％以下、硫黄０．０３ｗｔ％以下、
ケイ素１．０ｗｔ％以下、残部が主として鉄からなるオ
ーステナイト系ステンレス鋼に、ランタンまたはセリウ
ムを、０．５〜１．０ｗｔ％含有させたことを特徴とす
るオーステナイト鉄基合金。 ２、請求項１、記載の合金により構成されたことを特徴
とする原子炉炉内機器。[Claims] 1. 10.0 to 14.0 wt% nickel, 16. chromium.
0-18.0wt%, molybdenum 2.0-3.0wt%
, carbon 0.03wt% or less, manganese 2.0wt% or less, phosphorus 0.04wt% or less, sulfur 0.03wt% or less,
An austenitic iron-based alloy characterized by containing 0.5 to 1.0 wt % of lanthanum or cerium in an austenitic stainless steel consisting of 1.0 wt % or less of silicon and the remainder mainly iron. 2. A nuclear reactor in-core device comprising the alloy according to claim 1.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP16673390A JPH0456750A (en) | 1990-06-27 | 1990-06-27 | Austenitic iron base alloy |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP16673390A JPH0456750A (en) | 1990-06-27 | 1990-06-27 | Austenitic iron base alloy |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH0456750A true JPH0456750A (en) | 1992-02-24 |
Family
ID=15836743
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP16673390A Pending JPH0456750A (en) | 1990-06-27 | 1990-06-27 | Austenitic iron base alloy |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0456750A (en) |
-
1990
- 1990-06-27 JP JP16673390A patent/JPH0456750A/en active Pending
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