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核聚变与等离子体物理 ›› 2019, Vol. 39 ›› Issue (2): 151-157.DOI: 10.16568/j.0254-6086.201902009

• 核聚变工程技术 • 上一篇    下一篇

氘等离子体预辐照对W-Y2O3合金 耐热冲击性能的影响

谭 扬,练友运,封 范,陈 哲,王建豹,刘 翔*   

  1. (核工业西南物理研究院,成都 610041)
  • 收稿日期:2018-03-26 修回日期:2018-12-03 出版日期:2019-06-15 发布日期:2019-06-13
  • 作者简介:谭扬(1991-),男,重庆市开州区人,硕士,主要从事材料表面与等离子相互作用研究。
  • 基金资助:

    国家自然科学基金(11505049,11605044)

Effects of deuterium plasma pre-irradiation on the thermal shock resistance of HERF W-Y2O3 alloy

TAN Yang, LIAN You-yun, FENG Fan, CHEN Zhe, WANG Jian-bao, LIU Xiang   

  1. (Southwestern Institute of Physics, Chengdu 610041)
  • Received:2018-03-26 Revised:2018-12-03 Online:2019-06-15 Published:2019-06-13

摘要:

应用直线等离子体装置,对W-Y2O3合金的垂直于锻造轴(锻造面)和平行于锻造轴(横截面)的两个表面迚行了氘等离子体辐照。利用60kW电子束材料测试平台,研究了等离子体辐照前、后的W-Y2O3合金在功率0.22~0.44GW·m-2下耐瞬态热冲击性能。结果表明,氘等离子体辐照没有降低钨合金的裂纹阈值,其中锻造面的裂纹阈值范围高于横截面,且超过了0.33GW·m-2。综合考虑高能率锻造W-Y2O3合金的氘离子辐照与热冲击行为,锻造面可能更适合面对等离子体。

关键词: W-Y2O3合金, 高能率锻造, 氘等离子体, 瞬态热冲击, 裂纹阈值

Abstract:

The transient thermal shock resistance experiments of W-Y2O3 alloy before and after deuterium plasma irradiation were carried out on the 60kW Electronic-beam Materials testing Scenario (EMS-60) under the absorbed power density from 0.22GW·m-2 to 0.44GW·m-2. The consequences indicated that, low energy deuterium irradiation did not reduce the cracking thresholds of the W-Y2O3 alloy for both the forging plane (perpendicular to the forging axis) and its cross section plane (parallel to the forging axis), while the forging plane showed higher cracking threshold, surpassing 0.33GW·m-2. By comprehensive consideration, the transient thermal shock resistance and deuterium plasma irradiation behaviors of the high energy rate forging W-Y2O3, the forging plane may be more suitable for facing plasma.

Key words: W-Y2O3 alloy, High energy rate forging, Deuterium plasma, Transient thermal shocks, Cracking threshold

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