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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.
Bing Hong, Yunqing Bai, Gang Xu, Xiaoliang Zou
Nuclear Technology | Volume 204 | Number 1 | October 2018 | Pages 66-73
Technical Paper | doi.org/10.1080/00295450.2018.1464820
Articles are hosted by Taylor and Francis Online.
Lithium is an attractive coolant for space nuclear reactors due to its good thermal properties and low density. The main objective of this study is to investigate the effect of coolant 6Li concentration on the neutronic parameters of the lithium-cooled space reactor, with the aim to provide an appropriate reference for the purification of lithium coolant and the safety of the lithium-cooled space reactor. The neutronic calculations based on the lithium-cooled reactor are performed using the SuperMC code with the ENDF/B-VII cross-section database. The effects of coolant 6Li concentration were studied over the range of 0 to 8.5 at. % as well as the corresponding effects on the depletion, helium production, neutron spectrum, and temperature reactivity coefficient. The results show that the 6Li concentration of 0.01 at. % in the lithium coolant is appropriate in the lithium-cooled reactor. In this case, the neutronic parameters including the depletion, helium production, and neutron spectrum showed no obvious change compared to that of the pure 7Li, and the coolant reactivity coefficient has a negative effect on reactivity.
