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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.
D. Wootan, R. Omberg, A. Casella, N. Lahaye, B. Mcdowell (PNNL), W. Stokes (Columbia Basin Consulting Group)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 36-44
The accident scenarios that need to be analyzed within Chapter 15 of a safety analysis report may vary significantly between advanced reactors and the light water reactors that compose the current commercial fleet. In anticipation of identifying scenarios of concern and developing methods for their analysis, correlations may be made to calculations and tests performed in support of the liquid metal and molten salt reactors that have been operated previously within the US. In this paper, we discuss efforts made to compare Chapter 15 considerations for a proposed lead-bismuth cooled reactor to those developed previously for the Fast Flux Test Facility (FFTF) and the GE-Hitachi PRISM reactor. Comparisons were also made with Beyond Design Basis Accidents for FFTF.
