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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
X-energy receives federal tax credit for TRISO fuel facility
Advanced reactor company X-energy has been awarded $148.5 million in tax credits under the Inflation Reduction Act for construction of its TRISO-X fuel fabrication facility in Oak Ridge, Tenn.
Toshihide Takai, Tomohiro Furukawa, Hidemasa Yamano (JAEA)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 1007-1013
This paper describes estimation results of thermophysical properties of stainless steel (SS) containing 5mass% boron carbide (B4C) in the solid phase. First, we synthesized SS-B4C samples with emphasis on 5 mass%-B4C and SS using a hot press method. Homogeneity of our produced SS-B4C sample was evaluated by chemical composition analysis, metal structure observation, and micro X-ray diffraction (XRD). Both the density and specific heat of the SS-B4C sample were evaluated. These measurements proved that the density in our sample was lowered and the temperature dependence of the density, along with the elevation of temperature, became gradual compared to that of grade type 316L stainless steel (SUS316L) used as a reactor material by addition of B4C. The specific heat became slightly higher than that of SUS316L by addition of B4C and showed similar temperature dependence up to 800°C.