JP2668541B2 - Austenitic stainless steel for fusion reactor first wall member with excellent smoothing and flattening characteristics of melt surface during plasma disruption - Google Patents
Austenitic stainless steel for fusion reactor first wall member with excellent smoothing and flattening characteristics of melt surface during plasma disruptionInfo
- Publication number
- JP2668541B2 JP2668541B2 JP63054335A JP5433588A JP2668541B2 JP 2668541 B2 JP2668541 B2 JP 2668541B2 JP 63054335 A JP63054335 A JP 63054335A JP 5433588 A JP5433588 A JP 5433588A JP 2668541 B2 JP2668541 B2 JP 2668541B2
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- Prior art keywords
- stainless steel
- plasma disruption
- during plasma
- wall member
- fusion reactor
- Prior art date
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Classifications
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- 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
- Y02E30/10—Nuclear fusion reactors
Landscapes
- Treatment Of Steel In Its Molten State (AREA)
- Arc Welding In General (AREA)
- Plasma Technology (AREA)
Description
【発明の詳細な説明】 〔産業上の利用分野〕 本発明は、プラズマディスラプション時の溶融表面の
平滑・平坦化特性に優れた核融合炉の第一壁部材用オー
ステナイ系ステンレス鋼に関するものである。Description: TECHNICAL FIELD The present invention relates to an austenitic stainless steel for a first wall member of a fusion reactor, which is excellent in smoothing and flattening characteristics of a molten surface during plasma disruption. It is.
本発明において、プラズマディスラプションとは、プ
ラズマが瞬時に消滅する現象を意味する。In the present invention, plasma disruption refers to a phenomenon in which plasma is extinguished instantaneously.
核融合炉の第一壁は、従来の構造物にみられないほど
苛酷な環境下で使用されるため、その構成材料に対して
は極めて高い信頼性と健全性が要求される。何故なら
ば、核融合反応で発生したα粒子によって、第一壁には
定常的に高い熱負荷がかかるが、さらにプラズマディス
ラプションによって過渡的または局所的な超高熱負荷が
かかるためである。特に、プラズマディスラプション時
の熱負荷は通常の熱負荷の数十〜数百倍であり、それに
伴う部材の溶融・蒸発・凝固挙動や過大な熱応力に伴う
亀裂発生挙動等は、構造物の健全性確保の観点から重大
な関心が払われ、研究・解析が進められてきた。核融合
炉の第一壁部材には、日本原子力学会誌第29巻10号(19
87),P855に示されているようにSUS304やSUS316等のス
テンレス鋼、黒鉛、Mo、W、Ta、Alあるいは炭化珪素等
のセラミックス、等種々の材料が検討されているが、コ
ストや材料の供給性の観点からステンレス鋼は有望な材
料候補のひとつである。Since the first wall of a fusion reactor is used in a harsh environment that is not found in conventional structures, extremely high reliability and soundness are required for its constituent materials. The reason is that the α particles generated by the fusion reaction constantly apply a high heat load to the first wall, but the plasma disruption also applies a transient or local ultrahigh heat load. In particular, the heat load during plasma disruption is tens to hundreds of times the normal heat load, and the accompanying melting / evaporation / solidification behavior of members and the cracking behavior associated with excessive thermal stress, etc. A great deal of attention has been paid from the standpoint of ensuring the soundness of research, and research and analysis have been promoted. The first wall member of a fusion reactor includes the Atomic Energy Society of Japan, Vol. 29, No. 10 (19
87), various materials such as stainless steel such as SUS304 and SUS316, ceramics such as graphite, Mo, W, Ta, Al or silicon carbide as shown in P855 have been studied. From the viewpoint of availability, stainless steel is one of the promising material candidates.
しかし、最近のステンレス鋼を用いたプラズマディス
ラプション熱負荷模擬試験の結果では、同じ規格鋼種で
も材料間で溶融後の再凝固表面状態に差があることが指
摘されており、材料によっては表面が多数のクレーター
を伴って凹凸状になる。第一壁の場合、このような凹凸
状の溶融・再凝固挙動は、プラズマディスラプションの
繰返しによって選択的な板厚減少を惹き起こすため、核
融合炉の寿命を短くするとともに、寿命設計を難しくす
る。これは構造物の信頼性の観点から極めて好ましくな
い。寿命予測に基づいた設計の観点からは、プラズマデ
ィスラプションによる溶融後の表面は平滑・平坦である
ことが望まれる。しかし、従来これら高エネルギー下の
溶融・凝固挙動に及ぼす材質的な検討はほとんど行われ
ていない。However, recent plasma disruption heat load simulation tests using stainless steel indicate that there is a difference in the resolidification surface state after melting between materials even with the same standard steel grade, and depending on the material, the surface Becomes uneven with many craters. In the case of the first wall, this uneven melting / resolidification behavior causes a selective reduction in the thickness of the plate due to repeated plasma disruptions. Make it difficult. This is extremely undesirable from the viewpoint of the reliability of the structure. From the viewpoint of design based on life expectancy, the surface after melting by plasma disruption is desired to be smooth and flat. However, there has been almost no study on the properties of these materials on the melting / solidification behavior under high energy.
本発明はこのような背景からなされたものであり、プ
ラズマディスラプション時の表面溶融に対し凹凸状凝固
しない材料と、それを用いることを特徴とし寿命予測・
設計可能な信頼性の高い核融合炉の第一壁部材用オース
テナイト系ステンレス鋼を提供するものである。The present invention has been made from such a background, and is characterized by using a material that does not concavo-convexly solidify due to surface melting during plasma disruption, and uses it to predict life
An austenitic stainless steel for a first wall member of a fusion reactor that can be designed and has high reliability is provided.
すなわち、本発明者らは種々SUS304系及びSUS316系の
ステンレス鋼を用いて、プラズマディスラプション熱負
荷模擬試験をし、表面溶融挙動を検討した。That is, the present inventors conducted a plasma disruption heat load simulation test using various SUS304-based and SUS316-based stainless steels, and examined the surface melting behavior.
その結果、鋼中の微量元素の相違によって溶融後の表
面状態が顕著に変化するが、特に不可避的不純物元素で
ある硫黄(S)と酸素(O)の含有量増加によって溶融
後表面の凹凸状化(uneven化)が著しく促進されること
を見出した。例として第1図(a)にSを0.0195wt%含
有するSUS304タイプステンレス鋼のプラズマディスラプ
ション模擬試験後の溶融・凝固表面の模式図を示す。こ
れらの凹凸は、一度溶融後表面に形成されると、その後
の溶融・凝固の繰返しによって表面が平滑・平坦化(ev
en化)することはなく、凹凸は益々一方的に進行するこ
とも確認した。As a result, the surface condition after melting remarkably changes due to the difference in the trace elements in the steel, but the unevenness of the surface after melting especially due to the increase in the content of unavoidable impurity elements sulfur (S) and oxygen (O). (Unevenization) was found to be significantly promoted. As an example, FIG. 1 (a) shows a schematic diagram of the melting / solidifying surface of a SUS304 type stainless steel containing 0.0195 wt% S after a plasma disruption simulation test. Once these irregularities are formed on the surface after melting, the surface becomes smooth and flat by repeated melting and solidification (ev
en), and it was also confirmed that the irregularities progressed more and more unilaterally.
一方、これに対し、微量成分の効果を系統的に検討し
た結果、Al、Ti、REM、Caを単独あるいは複合で微量含
有させることによって、溶融後の表面が凹凸化しにくく
なることを見出し、さらにこの効果を安定化ならしめる
ためには有害な不純物元素であるS及びOの低減が有効
であることを見出した。第1図(b)にAl:0.071wt%及
びCa:0.005wt%を含有するSUS304タイプステンレス鋼の
プラズマディスラプション模擬試験後の溶融・凝固表面
の模式図を示すが、表面は第1図(a)のそれと比較し
て極めて平滑・平坦である。On the other hand, on the other hand, as a result of systematically examining the effect of the trace amount component, it was found that the surface after melting is less likely to be roughened by containing a trace amount of Al, Ti, REM, and Ca alone or in combination, and In order to stabilize this effect, it has been found that reduction of harmful impurity elements S and O is effective. FIG. 1 (b) is a schematic view of a molten and solidified surface of a SUS304 type stainless steel containing 0.071 wt% of Al and 0.005 wt% of Ca after a simulation test of plasma disruption. It is extremely smooth and flat as compared with that of (a).
すなわち、本発明の要旨とするところは、C:0.15wt%
以下、Si:1.0wt%以下、Mn:2.0wt%以下、Cr:16.0〜20.
0wt%、Ni:8.0〜15.0wt%、Mo:3.0wt%以下を含み、さ
らにTi:0.02〜0.1wt%、Al:0.02〜0.1wt%、REM:0.01〜
0.1wt%、Ca:0.003〜0.02wt%のうち一種または二種以
上を含有し、かつS:0.005wt%以下、O:0.007wt%以下で
あることを特徴とするプラズマディスラプション時の溶
融表面の平滑・平坦化特性に優れた核融合炉の第一壁部
材用オーステナイト系ステンレス鋼にある。That is, the gist of the present invention is as follows: C: 0.15 wt%
Hereinafter, Si: 1.0 wt% or less, Mn: 2.0 wt% or less, Cr: 16.0 to 20.
0 wt%, Ni: 8.0 to 15.0 wt%, Mo: 3.0 wt% or less, Ti: 0.02 to 0.1 wt%, Al: 0.02 to 0.1 wt%, REM: 0.01 to
Melting during plasma disruption characterized by containing one or more of 0.1 wt% and Ca: 0.003 to 0.02 wt%, and S: 0.005 wt% or less, O: 0.007 wt% or less An austenitic stainless steel for a first wall member of a fusion reactor having excellent surface smoothness and flattening characteristics.
次に本発明の成分限定理由を述べる。 Next, the reasons for limiting the components of the present invention will be described.
C,Si,Mn,Cr,Ni及びMoの組成については、製造性、コ
スト、材料特性等の観点から、SUS304及びSUS316を中心
としてSUS300番系オーステナイト系ステンレス鋼の成分
範囲にほぼ準じた。The composition of C, Si, Mn, Cr, Ni and Mo almost conformed to the component range of SUS300 series austenitic stainless steel centering on SUS304 and SUS316 from the viewpoint of manufacturability, cost, material properties and the like.
Sは不可避的不純物の一つの元素であり、プラズマデ
ィスラプション時の表面溶融挙動に著しく悪影響を与え
る。溶融表面の凹凸化傾向を低減するためには少なくと
も0.005wt%以下であることが必要である。S is one of the unavoidable impurities, and significantly affects the surface melting behavior at the time of plasma disruption. In order to reduce the tendency of the molten surface to be uneven, the content needs to be at least 0.005 wt% or less.
Oもまた、プラズマディスラプション時の表面溶融挙
動に著しく悪影響を与える。溶融表面の凹凸化傾向を低
減するためには少なくとも0.007wt%以下であることが
必要である。O also has a significant adverse effect on the surface melting behavior during plasma disruption. In order to reduce the tendency of the molten surface to be uneven, the content needs to be at least 0.007 wt% or less.
Tiは、少なくとも0.02wt%以上の含有によってプラズ
マディスラプション時の溶融表面の凹凸化傾向を低減し
平滑化を促進するが、0.1wt%を超えて含有するとその
効果が認められないことから、0.02wt%以上0.1wt%以
下とした。Ti promotes smoothing by reducing the unevenness tendency of the molten surface during plasma disruption by containing at least 0.02 wt% or more, but if the content exceeds 0.1 wt%, its effect is not recognized, 0.02 wt% or more and 0.1 wt% or less.
Alは製鋼反応において脱酸剤として用いられるが、同
時に0.02wt%以上の含有によってプラズマディスラプシ
ョン時の溶融表面の凹凸化傾向を低減し平滑化を促進す
る効果がある。他方0.1wt%を超えて含有するとその効
果が認められず、また鋼板の溶接性も低下させることか
ら、範囲を0.02wt%以上0.1wt%以下とした。Al is used as a deoxidizing agent in the steelmaking reaction, and at the same time, the content of 0.02 wt% or more has the effect of reducing the uneven surface tendency of the molten surface during plasma disruption and promoting smoothing. On the other hand, if the content exceeds 0.1 wt%, the effect is not recognized and the weldability of the steel sheet is also deteriorated, so the range was made 0.02 wt% or more and 0.1 wt% or less.
REMはLa,Ce等のいわゆる希土類元素及びその混合物を
指し、0.01wt%以上の含有でプラズマディスラプション
時の溶融表面の平滑化に効果があるが、0.1wt%を越え
て含有すると鋼板の製造性が低減するため、上限を0.1w
t%とした。REM refers to so-called rare earth elements such as La and Ce and their mixtures. A content of 0.01 wt% or more has the effect of smoothing the molten surface during plasma disruption, but a content of more than 0.1 wt% reduces the steel sheet. Manufacturability is reduced, so the upper limit is 0.1w
t%.
Caは製鋼反応において脱酸、脱硫剤として用いられる
が、同時に、0.003wt%以上の含有でプラズマディスラ
プション時の溶融表面の平滑化に効果がある。しかし、
0.02wt%を越えて含有すると鋼板の製造性が低減するた
め、上限を0.02wt%とした。Ca is used as a deoxidizing agent and a desulfurizing agent in the steelmaking reaction, but at the same time, if it is contained in an amount of 0.003 wt% or more, it is effective in smoothing the molten surface during plasma disruption. But,
If the content exceeds 0.02 wt%, the productivity of the steel sheet is reduced, so the upper limit is made 0.02 wt%.
なお、残部はFeおよびS,O以外の不可避的不純物であ
り、P,Nはそれぞれ0.04wt%、0.08wt%以下であればよ
い。The balance is inevitable impurities other than Fe, S, and O, and P and N may be 0.04 wt% and 0.08 wt% or less, respectively.
以下に実施例を挙げて詳細に説明する。 The present invention will be described in detail below with reference to examples.
SUS304系、SUS316系をベースに、微量元素を変化させ
た種々のステンレス鋼を作製した。これらは真空溶解
後、熱間圧延によって5mm厚の鋼板とし、1050℃30分の
固溶化処理をして実験に供した。これらの化学組成及び
同じく実験に供した市販SUS304,316の化学組成を第1表
に示す。表中No.1〜14は本発明鋼であり、No.15〜26は
比較鋼である。Various stainless steels were prepared based on SUS304 and SUS316 with different trace elements. These were melted in vacuum and then hot-rolled into a steel plate having a thickness of 5 mm. Table 1 shows these chemical compositions and the chemical compositions of commercially available SUS304 and 316 which were also subjected to the experiment. In the table, Nos. 1 to 14 are steels of the present invention, and Nos. 15 to 26 are comparative steels.
これらの鋼板から4mm t×50mm×20mmの試験片を切出
し、表面を#400番研磨して試験片を作製した。実験は
ビームエネルギー120KeVの水素イオンビームを用い、プ
ラズマディスラプション模擬試験を行った。ビーム照射
時間は20〜250msであり、この間の熱流束は80MW/m2であ
った。照射後の試験片の溶融表面性状を観察し、平滑・
平坦(even)、一部凹凸(partially uneven)、及び凹
凸(uneven)の3段階に分類した。すでに述べたように
照射後の表面としては完全に平滑・平坦なもの(even)
が材料として望ましい。実験の結果を化学成分と併せて
第1表に示す。これよりS:0.005wt%あるいはO:0.007wt
%を越えると、プラズマ照射後の表面性状がevenからun
evenに遷移するのは明らかである。また、これら不純物
元素量を低く抑えたのみでは例えばNo.21に見られるよ
うち部分的にuneven化するケースもあり、表面のeven化
を安定化ならしめるためTi,Al,REM,Caの添加効果は明ら
かである。他方、No.24や25に見られるように過剰なAl,
Tiの含有は、むしろ溶融・凝固後の表面性状には有害で
ある。したがってS,O量を低く抑え、かつTi,Al,REM,Ca
の一種または二種以上を適量含有することが、プラズマ
ディスラプション時の溶融・凝固表面を平滑・平坦化す
るのに有効であることが明らかとなった。 A test piece of 4 mm t × 50 mm × 20 mm was cut out from these steel sheets, and the surface was polished with # 400 to prepare a test piece. In the experiment, a plasma disruption simulation test was performed using a hydrogen ion beam with a beam energy of 120 KeV. The beam irradiation time was 20-250 ms, during which the heat flux was 80 MW / m 2 . Observe the molten surface properties of the test specimen after irradiation, and
It was classified into three stages: even, partially uneven, and uneven. As already mentioned, the surface after irradiation is completely smooth and flat (even)
Is desirable as a material. The results of the experiment are shown in Table 1 together with the chemical components. From this, S: 0.005wt% or O: 0.007wt
%, The surface quality after plasma irradiation is from even to un
The transition to even is clear. In addition, there are cases in which only a slight amount of these impurity elements is suppressed, for example, as shown in No. 21, there is a case where it becomes partially uneven.Therefore, addition of Ti, Al, REM, and Ca to stabilize even conversion of the surface. The effect is clear. On the other hand, excess Al, as seen in Nos. 24 and 25,
The inclusion of Ti is rather harmful to the surface properties after melting and solidification. Therefore, the amount of S, O is kept low and Ti, Al, REM, Ca
It has been clarified that the appropriate content of one or more of the above is effective for smoothing and flattening the melted / solidified surface during plasma disruption.
核融合炉の第一壁用部材に使用されるステンレス鋼に
おいて、S,O量を低く抑え、かつTi,Al,REM,Caの一種ま
たは二種以上を適量含有させることによって、プラズマ
ディスラプション時の溶融・凝固挙動の異常化(表面凹
凸化)を抑えることができる。また、これを用いた核融
合炉においては第一壁のプラズマディスラプションによ
る材料損傷が設計上予測可能になり、構造物の信頼性、
健全性が高まる。In the stainless steel used for the first wall member of the fusion reactor, the amount of S, O is kept low, and by containing an appropriate amount of one or more of Ti, Al, REM, and Ca, plasma disruption Abnormality of the melting / solidification behavior at the time (surface unevenness) can be suppressed. Also, in a fusion reactor using this, material damage due to plasma disruption of the first wall can be predicted by design, and reliability of the structure,
Increases soundness.
第1図(a)はSを0.0195wt%含有するSUS304タイプス
テンレス鋼(18.9Cr−9.0Ni、第1表中No.15)のプラズ
マディスラプション模擬試験後の溶融・凝固表面の模式
図、第1図(b)はS:0.0010wt%、Al:0.071wt%及びC
a:0.005wt%を含有するSUS304タイプステンレス鋼(18.
4Cr−8.5Ni、第1表中No.4)のプラズマディスラプショ
ン模擬試験後の溶融・凝固表面の模式図である。FIG. 1 (a) is a schematic view of a molten / solidified surface of a SUS304 type stainless steel (18.9Cr-9.0Ni, No. 15 in Table 1) containing 0.0195 wt% of S after a plasma disruption simulation test. Fig. 1 (b) shows S: 0.0010wt%, Al: 0.071wt% and C
a: SUS304 type stainless steel containing 0.005wt% (18.
FIG. 4 is a schematic diagram of a melting / solidifying surface of 4Cr-8.5Ni, No. 4 in Table 1) after a simulated plasma disruption test.
───────────────────────────────────────────────────── フロントページの続き (72)発明者 櫻井 英夫 神奈川県相模原市淵野辺5―10―1 新 日本製鐵株式會社第2技術研究所内 (72)発明者 井上 裕滋 神奈川県相模原市淵野辺5―10―1 新 日本製鐵株式會社第2技術研究所内 (72)発明者 班目 春樹 東京都文京区小日向1―16―3 (56)参考文献 特開 昭59−182956(JP,A) 特開 昭59−110767(JP,A) 特開 昭57−85956(JP,A) 実開 昭54−112719(JP,U) ─────────────────────────────────────────────────── ─── Continuation of the front page (72) Inventor Hideo Sakurai 5-10-1 Fuchinobe, Sagamihara-shi, Kanagawa 2nd Technical Research Laboratory, Nippon Steel Corp. (72) Hiroshi Inoue 5-10 Fuchinobe, Sagamihara-shi, Kanagawa ―1 Inside Nippon Steel Co., Ltd. 2nd Technical Research Laboratory (72) Inventor Haruki 1-16-3 Kohinata, Bunkyo-ku, Tokyo (56) Reference JP-A-59-182956 (JP, A) JP-A- 59-110767 (JP, A) JP-A-57-85956 (JP, A) Actually developed 54-112719 (JP, U)
Claims (1)
溶融表面の平滑・平坦化特性に優れた核融合炉の第一壁
部材用オーステナイト系ステンレス鋼。[Claim 1] C: 0.15 wt% or less, Si: 1.0 wt% or less, Mn: 2.0 wt% or less, Cr: 16.0 to 20.0 wt%, Ni: 8.0 to 15.0 wt%, Mo: 3.0 wt% or less , Further contains one or more of Ti: 0.02 to 0.1 wt%, Al: 0.02 to 0.1 wt%, REM: 0.01 to 0.1 wt%, Ca: 0.003 to 0.02 wt%, and S: 0.005 wt% Below, O: 0.007 wt% or less is an austenitic stainless steel for the first wall member of a fusion reactor, which has excellent smoothing and flattening characteristics of the molten surface during plasma disruption.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63054335A JP2668541B2 (en) | 1988-03-08 | 1988-03-08 | Austenitic stainless steel for fusion reactor first wall member with excellent smoothing and flattening characteristics of melt surface during plasma disruption |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63054335A JP2668541B2 (en) | 1988-03-08 | 1988-03-08 | Austenitic stainless steel for fusion reactor first wall member with excellent smoothing and flattening characteristics of melt surface during plasma disruption |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH01230753A JPH01230753A (en) | 1989-09-14 |
| JP2668541B2 true JP2668541B2 (en) | 1997-10-27 |
Family
ID=12967732
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP63054335A Expired - Fee Related JP2668541B2 (en) | 1988-03-08 | 1988-03-08 | Austenitic stainless steel for fusion reactor first wall member with excellent smoothing and flattening characteristics of melt surface during plasma disruption |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2668541B2 (en) |
Family Cites Families (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS605668B2 (en) * | 1978-02-24 | 1985-02-13 | 住友金属工業株式会社 | Non-magnetic steel with good electron beam weldability |
| JPS5785956A (en) * | 1980-11-14 | 1982-05-28 | Sumitomo Metal Ind Ltd | Structural material of nuclear reactor core used in water-cooled environment |
| JPS59110767A (en) * | 1982-12-14 | 1984-06-26 | Sumitomo Metal Ind Ltd | Austenite stainless steel |
| JPS59182956A (en) * | 1983-04-02 | 1984-10-17 | Nippon Steel Corp | High-alloy stainless steel with superior hot workability |
-
1988
- 1988-03-08 JP JP63054335A patent/JP2668541B2/en not_active Expired - Fee Related
Also Published As
| Publication number | Publication date |
|---|---|
| JPH01230753A (en) | 1989-09-14 |
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| LAPS | Cancellation because of no payment of annual fees |