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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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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.
Sanjay Gupta, Feroz Ahmed, Suresh Garg
Nuclear Science and Engineering | Volume 125 | Number 3 | March 1997 | Pages 362-370
Technical Paper | doi.org/10.13182/NSE97-A24281
Articles are hosted by Taylor and Francis Online.
Results are reported for the space-dependent neutron spectra and tritium breeding ratio (TBR) in a proposed Li + C blanket of a deuterium-tritium fusion reactor. The multigroup diffusion equation is solved as an eigenvalue problem for three concentrations of lithium in graphite. The effect on the value of TBR of increasing the fraction of low-energy neutrons in a completely thermalized source is studied. A comparison of neutron spectra as obtained in the Li + C and 3He + C systems is also made. The results show that TBR increases with the concentration of lithium in graphite as well as with the fraction of low-energy neutrons in the source. [Essentially the same value of TBR (= 0.277) is obtained for the Li + C system with a lithium to graphite concentration of 4 x 10-2 as for a 3He + C system with a natural density of 3He.] Moreover, TBR attains an almost constant value for assembly thicknesses greater than -20 cm. Also, if a source with an increased fraction of low-energy neutrons is used, the effect is more pronounced in the 3He + C system for the range of lithium concentrations considered.
