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Nuclear Technology Volume 205, 2019 - Issue 5
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Technical Papers

Total Hemispherical Emissivity of Potential Structural Materials for Very High Temperature Reactor Systems: Alloy 617

Kyle L. WaltonUniversity of Missouri, Nuclear Science and Engineering Institute and Particulate Systems Research Center, Columbia, Missouri65211
,
Raymond K. MaynardUniversity of Missouri, Nuclear Science and Engineering Institute and Particulate Systems Research Center, Columbia, Missouri65211
,
Tushar K. GhoshUniversity of Missouri, Nuclear Science and Engineering Institute and Particulate Systems Research Center, Columbia, Missouri65211
,
Robert V. TompsonUniversity of Missouri, Nuclear Science and Engineering Institute and Particulate Systems Research Center, Columbia, Missouri65211
,
Dabir S. ViswanathUniversity of Missouri, Nuclear Science and Engineering Institute and Particulate Systems Research Center, Columbia, Missouri65211
&
Sudarshan K. LoyalkaUniversity of Missouri, Nuclear Science and Engineering Institute and Particulate Systems Research Center, Columbia, Missouri65211Correspondence[email protected]
Pages 684-693 | Received 09 May 2018, Accepted 04 Sep 2018, Published online: 25 Oct 2018

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Faten N. Al Zubaidi, Kyle L. Walton, Robert V. Tompson, Tushar K. Ghosh & Sudarshan K. Loyalka. (2021) Emissivity of Grade 91 Ferritic Steel: Additional Measurements on Role of Surface Conditions and Oxidation. Nuclear Technology 207:8, pages 1257-1269.
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Yanlei Liu, Junyuan Liu, Daqing Yuan, Kun Yu, Zilong Liu, Zhiying Chen & Yufang Liu. (2023) The measurement and modeling investigation on the in- and out-of-plane polarized BRDF of alumina in the near-infrared region. Optik 288, pages 171109.
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Yan Zhang, Yuxin Yang, Long Wu, Jin Wang, Qing Liu & Yuzhong Zhang. (2023) Normal spectral emissivity characteristics of tungsten in the mid-infrared region. Journal of Instrumentation 18:05, pages T05005.
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Qingxiang Hu, Kun Yuan, Wei Peng, Gang Zhao & Jie Wang. (2021) A numerical study of heat transfer enhancement by helically corrugated tubes in the intermediate heat exchanger of a very-high-temperature gas-cooled reactor. Nuclear Engineering and Design 380, pages 111275.
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