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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
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.
