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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.
J. R. Brown, R. Hackney, V. Malakhof, W. A. Simon
Nuclear Science and Engineering | Volume 97 | Number 2 | October 1987 | Pages 104-122
Technical Paper | doi.org/10.13182/NSE87-A27459
Articles are hosted by Taylor and Francis Online.
Fort St. Vrain (FSV) is the only graphite-moderated, helium-cooled nuclear power plant in the United States. It was preceded by the 40-MW(electric) Peach Bottom high-temperature gas-cooled reactor (HTGR), which was permanently shut down in 1975. The Public Service Company of Colorado owns and operates FSV, and the core design and manufacture were performed by General Atomic Company (now GA Technologies, Inc.). Extensive physics testing of the 330-MW(electric) FSV HTGR was conducted to confirm the adequacy of the calculational models used in the core design. The physics testing performed during the first three cycles has confirmed that the calculational models used for the core design have been eminently successful in predicting the core nuclear performance from initial cold criticality through power operation and refueling.