首页> 外文会议>IEA International Workshop on Beryllium Technology for Fusion; 20031202-20031205; Miyazaki; JP >Thermal Cycling of Activity Cooled Be/CuCrZr and Be/GlidCop Mock-ups in a Core of Nuclear Reactor
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Thermal Cycling of Activity Cooled Be/CuCrZr and Be/GlidCop Mock-ups in a Core of Nuclear Reactor

机译:核反应堆芯中活动冷却的Be / CuCrZr和Be / GlidCop模型的热循环

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Proposing beryllium as plasma facing armour and fast brazing as Be/Cu-alloy joining technique, this paper presents the recent experimental results. It was shown that fast brazing of Be onto both PH-copper like CuCrZr and DS-copper like GlidCop provides reliable joint that does not failure under heat flux up to melting of Be surface. Investigating the influence of neutron irradiation on Be/Cu-alloy joint behaviour, in-pile integrated test in a core of nuclear reactor CM-2, Dimitrovgrad, Russia was carried out. In this test actively cooled Be/CuCrZr and Be/GlidCop joints were simultaneously subjected to high heat flux (1000 cycles, ~7.5 MW/m~2) and neutron irradiation (total fluence 2.8xl0~(20) n/cm~2, -0.13 dpa). Both type of tested joints successfully survived applied heat and neutron loads. Optic and TEM metallography before and after irradiation as well as microhardness measurements are presented and discussed.
机译:提出了将铍作为等离子面对装甲,并采用快速钎焊作为Be / Cu合金连接技术,提出了最新的实验结果。结果表明,将Be快速钎焊到类似CuCrZr的PH铜和类似GlidCop的DS铜上,提供了可靠的连接,在热流直至Be表面熔化的情况下都不会失效。为了研究中子辐照对Be / Cu合金联合行为的影响,在俄罗斯Dimitrovgrad核反应堆CM-2的堆芯中进行了堆内综合测试。在该测试中,主动冷却的Be / CuCrZr和Be / GlidCop接头同时经受高热通量(1000个循环,约7.5 MW / m〜2)和中子辐照(总通量为2.8xl0〜(20)n / cm〜2, -0.13 dpa)。两种类型的测试接头都成功地承受了施加的热和中子载荷。介绍并讨论了辐照前后的光学和TEM金相学以及显微硬度测量。

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