Effect of potassium bubbles on the thermal shock fatigue behavior of large-volume potassium-doped tungsten alloy

被引:13
作者
Ma, Xiaolei [1 ]
Feng, Fan [2 ]
Zhang, Xiaoxin [1 ]
Wang, Ting [3 ]
Liu, Xiang [2 ]
Lv, Wei [4 ]
Lang, Shaoting [5 ]
Ge, Changchun [1 ]
Yan, Qingzhi [1 ]
机构
[1] Univ Sci & Technol Beijing, Inst Nucl Mat, Sch Mat Sci & Engn, Beijing 100083, Peoples R China
[2] Southwestern Inst Phys, Chengdu 610041, Sichuan, Peoples R China
[3] Beihang Univ, Sch Phys, Beijing 100191, Peoples R China
[4] North China Elect Power Univ, Inst Energy Power Innovat, Beijing 102206, Peoples R China
[5] Xinxiang Univ, Mech & Elect Engn, Xinxiang 453000, Henan, Peoples R China
基金
中国国家自然科学基金;
关键词
potassium-doped tungsten alloy; potassium bubble strings; transient thermal shock; microstructure; formation and propagation of cracks; MECHANICAL-PROPERTIES; MICROSTRUCTURE; RESISTANCE; RECRYSTALLIZATION; MORPHOLOGY; STRENGTH; IMPACT;
D O I
10.1088/1741-4326/ac9a5b
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
A newly developed large-volume potassium-doped tungsten (W-K) plate with a thickness of 15 mm and a weight of 25 kg by powder metallurgy plus hot rolling was prepared to meet the requirements of the International Thermonuclear Experimental Reactor (ITER) in engineering application. In order to clarify the effect of K doping on the thermal shock performance of W-K alloy, transient thermal shock tests with a single-pulse duration of 1 ms for 100 shots at room temperature were performed. The absorbed power density is set to 0.33, 0.44, 0.55 and 0.66 GW m(-2), respectively. Furthermore, the microstructure, Vickers micro-hardness before and after the transient thermal shock, thermal conductivity and relative density were also characterized. The results indicate that the cracking threshold of rolled W-K is 0.44-0.55 GW m(-2), which possesses a better transient thermal shock resistance compared with the most of advanced W-based materials. This is mainly because K doping can significantly improve the high-temperature stability and mechanical properties of W material without reducing its thermal conductivity. In particular, K bubbles can also effectively inhibit the formation and propagation of cracks during thermal shock. Moreover, the cracking mechanism of rolled W-K alloy is also discussed in detail. This study is helpful for building a trusted ITER database on advanced W-based materials that provides useful references for the selection of future plasma-facing materials.
引用
收藏
页数:15
相关论文
共 65 条
  • [1] Thermal stability of a highly-deformed warm-rolled tungsten plate in the temperature range 1100-1250 °C
    Alfonso, A.
    Jensen, D. Juul
    Luo, G. -N.
    Pantleon, W.
    [J]. FUSION ENGINEERING AND DESIGN, 2015, 98-99 : 1924 - 1928
  • [2] Effects of vanadium concentration on the densification, microstructures and mechanical properties of tungsten vanadium alloys
    Arshad, Kameel
    Zhao, Ming-Yue
    Yuan, Yue
    Zhang, Ying
    Zhao, Zhen-Hua
    Wang, Bo
    Zhou, Zhang-Jian
    Lu, Guang-Hong
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2014, 455 (1-3) : 96 - 100
  • [3] EFFECT OF DISLOCATION SELF-INTERACTION ON OROWAN STRESS
    BACON, DJ
    KOCKS, UF
    SCATTERGOOD, RO
    [J]. PHILOSOPHICAL MAGAZINE, 1973, 28 (06) : 1241 - 1263
  • [4] Microstructure and mechanical properties of a W-2wt.%Y2O3 composite produced by sintering and hot forging
    Battabyal, M.
    Schaeublin, R.
    Spaetig, P.
    Walter, M.
    Rieth, M.
    Baluc, N.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2013, 442 (1-3) : S225 - S228
  • [5] Chemically produced tungsten-praseodymium oxide composite sintered by spark plasma sintering
    Ding, Xiao-Yu
    Luo, Lai-Ma
    Lu, Ze-Long
    Luo, Guang-Nan
    Zhu, Xiao-Yong
    Cheng, Ji-Gui
    Wu, Yu-Cheng
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2014, 454 (1-3) : 200 - 206
  • [6] ANISOTROPY IN THE MECHANICAL PROPERTIES OF POTASSIUM AND RHENIUM DOPED TUNGSTEN ALLOY PLATES FOR FUSION REACTOR APPLICATIONS
    Fukuda, Makoto
    Nogami, Shuhei
    Yabuuchi, Kiyohiro
    Hasegawa, Akira
    Muroga, Takeo
    [J]. FUSION SCIENCE AND TECHNOLOGY, 2015, 68 (03) : 690 - 693
  • [7] Microstructure development of dispersion-strengthened tungsten due to neutron irradiation
    Fukuda, Makoto
    Hasegawa, Akira
    Nogami, Shuhei
    Yabuuchi, Kiyohiro
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2014, 449 (1-3) : 213 - 218
  • [8] Thermal properties of pure tungsten and its alloys for fusion applications
    Fukudal, Makoto
    Hasegawa, Akira
    Nogami, Shuhei
    [J]. FUSION ENGINEERING AND DESIGN, 2018, 132 : 1 - 6
  • [9] Performance of deformed tungsten under ELM-like plasma exposures in QSPA Kh-50
    Garkusha, I. E.
    Landman, I.
    Linke, J.
    Makhlaj, V. A.
    Medvedev, A. V.
    Malykhin, S. V.
    Peschanyi, S.
    Pintsuk, G.
    Pugachev, A. T.
    Tereshin, V. I.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2011, 415 (01) : S65 - S69
  • [10] ITER tungsten divertor design development and qualification program
    Hirai, T.
    Escourbiac, F.
    Carpentier-Chouchana, S.
    Fedosov, A.
    Ferrand, L.
    Jokinen, T.
    Komarov, V.
    Kukushkin, A.
    Merola, M.
    Mitteau, R.
    Pitts, R. A.
    Shu, W.
    Sugihara, M.
    Riccardi, B.
    Suzuki, S.
    Villari, R.
    [J]. FUSION ENGINEERING AND DESIGN, 2013, 88 (9-10) : 1798 - 1801