Numerical Heat Transfer and Fluid Flow
Численное теплоперенос и движение жидкостей
1981-06-01
SCID: 54.1/7z73azxw
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Fluid flowLiquid-metal heat transferNumerical heat transferThermal and hydraulic computer codes
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Abstract (AI)
"Numerical Heat Transfer and Fluid Flow." Nuclear Science and Engineering, 78(2), pp. 196–197 Additional informationNotes on contributorsChia-Jung HsuAbout the Reviewer: C. J. Hsu has been at Brookhaven National Laboratory for over 18 years as a chemical engineer and a member of the scientific staff of the Department of Nuclear Energy. He also served as adjunct professor of mechanical engineering at the Cooper Union for the Advancement of Science and Art in New York City. Although his theoretical research interests were in the fields of fluid dynamics and liquid-metal heat transfer, during the past several years he has been involved mainly in the development and applications of thermal and hydraulic computer codes related to nuclear reactor safety analyses. Dr. Hsu holds graduate degrees from Columbia University and the University of Houston.
Key Findings
1
C. J. Hsu's recent work focused mainly on developing and applying thermal and hydraulic computer codes for nuclear reactor safety analyses.
2
Hsu's theoretical research interests include fluid dynamics and liquid-metal heat transfer, informing his perspective on numerical heat transfer and fluid flow.
3
Reviewer C. J. Hsu has extensive experience (over 18 years) at Brookhaven National Laboratory in chemical engineering and nuclear energy-related scientific work.
4
The document is a review or note concerning the subject 'Numerical Heat Transfer and Fluid Flow' published in Nuclear Science and Engineering, 78(2), pp.196–197.
Research Object
numerical heat transfer and fluid flow models (computational simulations)
Research Subject
development, application, and validation of thermal and hydraulic computer codes for simulating heat transfer and fluid flow, especially for reactor safety analyses
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1981-06-01
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