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首页> 外文期刊>Nuclear engineering and technology >HIGH HEAT FLUX TEST WITH HIP BONDED 35X35X3 BE/CU MOCKUPS FOR THE ITER BLANKET FIRST WALL
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HIGH HEAT FLUX TEST WITH HIP BONDED 35X35X3 BE/CU MOCKUPS FOR THE ITER BLANKET FIRST WALL

机译:带热粘合35X35X3 BE / CU样机的热通量测试,用于ITER毛毯第一壁

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摘要

To develop the manufacturing methods for the blanket first wall (FW) of the International Thermonuclear Experimental Reactor (ITER) and to verify the integrity of the joint, Be/Cu mockups were fabricated and tested at the KoHLT-1 (Korea Heat Load Test facility), a graphite heater facility located at the Korea Atomic Energy Research Institute (KAERI). Since Be and Cu joining is the focus of the present study, the fabricated mockups had a CuCrZr heat sink joined with three Be tiles as an armor material, unlike the original ITER blanket FW, which has a stainless steel structure and coolant tubes. Hot isostatic pressing (HIP) was carried out at 580 °C and 100 MPa for 2 hours as the method for Be/Cu joining. Three interlayers, namely, 1 μmCr/10μmCu, 1 μmTi/0.5μmCr/10μmCu, and 5μmTi/l0μmCu were applied as a coating to the Be tiles by a physical vapor deposition (PVD) method. A shear test was performed with the specimens, which were fabricated by the same methods as those used to fabricate the mockups. The average values were 125 MPa to 180 MPa, and the samples with the 1 μmCr/l0μmCu interlayer showed the lowest value. No defect or delamination was found in the joints of the mockups by the developed ultrasonic test using a flat-type probe with a 10 MHz frequency and a 0.25 inch diameter. High heat flux (HHF) tests were performed at 1.0 MW/m2 heat flux for each mockup using the given conditions, and the results were analyzed by ANSYS-CFX code. For the test criteria, an expected fatigue lifetime about 1,000 cycles was obtained by analysis with ANSYS-mechanical code. Mockups using the interlayers of lμTi/0.5μmCr/l0μmCu and 5μmTi/l0μmCu survived up to 1,100 cycles over the required number of cycles. However, one of the Be tiles in the other two mockups using the 1 μmCr/l0μmCu interlayer was detached during the screening test, and others were detached by discharge after 862 cycles. The integrity of the joints using the proposed interlayers was proven by the HHF test, but the other interlayer requires more study before it can be used for the joining of Be to Cu. Moreover, it was confirmed that the measured temperatures agreed well with the analysis temperatures, which were used to estimate the lifetime and that the developed facility showed its capability of the long time operation.
机译:为了开发国际热核实验堆(ITER)的毯式第一壁(FW)的制造方法并验证接头的完整性,在KoHLT-1(韩国热负荷测试设施)制造并测试了Be / Cu样机),这是位于韩国原子能研究所(KAERI)的石墨加热器设施。由于Be和Cu的接合是本研究的重点,因此,与原始的ITER毯子FW不同,该模型具有一个CuCrZr散热器和三个Be砖作为装甲材料,该ICr毯子FW具有不锈钢结构和冷却剂管。作为Be / Cu接合的方法,在580℃和100MPa下进行2小时的热等静压(HIP)。通过物理气相沉积(PVD)方法将3个中间层(即1μmCr/10μmCu,1μmTi/0.5μmCr/10μmCu和5μmTi/10μmCu)用作Be瓷砖的涂层。用与用于制造模型的方法相同的方法制造的样品进行剪切测试。平均值为125 MPa至180 MPa,夹层为1μmCr/10μmCu的样品显示最低值。使用频率为10 MHz,直径为0.25英寸的扁平型探头,通过开发的超声波测试,在样机的接头中未发现任何缺陷或分层。在给定条件下,对每个样机以1.0 MW / m2的热通量进行了高热通量(HHF)测试,并通过ANSYS-CFX代码对结果进行了分析。对于测试标准,通过使用ANSYS机械代码进行分析可获得预期的约1,000个循环的疲劳寿命。使用1μTi/0.5μmCr/10μmCu和5μmTi/10μmCu的中间层的模型在所需的循环数下最多可以保留1,100个循环。但是,在其他两个模型中使用1μmCr/10μmCu夹层的Be瓷砖之一在筛选测试期间分离,而其他元素在862个循环后通过放电分离。使用所建议的中间层的接头的完整性已通过HHF测试证明,但是另一个中间层需要更多的研究才能用于将Be与Cu连接。此外,已确认测得的温度与分析温度非常吻合,分析温度可用于估计寿命,并且所开发的设备具有长期运行的能力。

著录项

  • 来源
    《Nuclear engineering and technology 》 |2010年第6期| p.662-669| 共8页
  • 作者单位

    Korea Atomic Energy Research InstituteDaedeokdaero 1045, Yuseong-gu, Daejeon, 305-600, Republic of Korea;

    Korea Atomic Energy Research InstituteDaedeokdaero 1045, Yuseong-gu, Daejeon, 305-600, Republic of Korea;

    Korea Atomic Energy Research InstituteDaedeokdaero 1045, Yuseong-gu, Daejeon, 305-600, Republic of Korea;

    Korea Atomic Energy Research InstituteDaedeokdaero 1045, Yuseong-gu, Daejeon, 305-600, Republic of Korea;

    Korea Atomic Energy Research InstituteDaedeokdaero 1045, Yuseong-gu, Daejeon, 305-600, Republic of Korea;

    Korea Atomic Energy Research InstituteDaedeokdaero 1045, Yuseong-gu, Daejeon, 305-600, Republic of Korea;

    Korea Atomic Energy Research InstituteDaedeokdaero 1045, Yuseong-gu, Daejeon, 305-600, Republic of Korea;

    National Fusion Research InstituteGwahangno 113, Yuseong-gu, Daejeon, 305-333, Republic of Korea;

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  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    iter; first wall; hip; be/cu mockup; hhf test;

    机译:反复第一壁臀部是/ cu样机;高频测试;

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