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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
Excelsior University student section awarded community education grant
The American Nuclear Society Student Section at Excelsior University in Albany, N.Y., was awarded a $5,000 grant from the ANS Student Section Strategic Fund initiative for its program, Empowering Tomorrow’s Nuclear Innovators: A Collaborative Approach to Nuclear Technology Education and Awareness.
Toshihide Takai, Tomohiro Furukawa, Hidemasa Yamano
Nuclear Technology | Volume 205 | Number 9 | September 2019 | Pages 1164-1174
Technical Paper | doi.org/10.1080/00295450.2019.1607136
Articles are hosted by Taylor and Francis Online.
This paper describes evaluation results of thermophysical properties of stainless steel (SS) containing 5 mass % boron carbide (B4C) in its solid phase. First, the authors synthesized SS-B4C samples with emphasis on 5 mass % B4C and SS using a hot press method and then evaluated its homogeneity in several ways, such as chemical composition analysis, metallographic structure observation, and micro X-ray diffraction. This study also evaluated the density and the specific heat and thermal conductivity of the SS-B4C sample and found that the density becomes lower and the temperature dependence of the density decreased as the temperature rose compared to that of stainless steel Type 316L (SS316L) used as a reactor material. The specific heat became slightly higher than that of SS316L and showed similar temperature dependence up to 1073 K. Unexpectedly, the thermal conductivity became lower than that of SS316L and showed similar temperature dependence up to 1273 K.