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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.
R. T. Santoro, R. A. Lillie, R. G. Alsmiller, Jr., J. M. Barnes
Nuclear Science and Engineering | Volume 70 | Number 3 | June 1979 | Pages 225-242
Technical Paper | doi.org/10.13182/NSE79-A20145
Articles are hosted by Taylor and Francis Online.
Two- and three-dimensional radiation transport methods have been employed to estimate the nuclear performance of the neutral beam injectors being designed for the Tokamak Fusion Test Reactor. The nuclear heating rates and neutron and gamma-ray energy spectra have been calculated at various locations in a detailed calculational model of the injector using Monte Carlo methods. Calculations have also been carried out using discrete-ordinates methods to obtain estimates of these data in a two-dimensional model of the injector. The two-dimensional calculational procedure was developed as an analytic tool for more cost-efficient scoping and parametric studies of the effects of design changes on the injector performance due to the streaming of 14-MeV neutrons. The nuclear responses and spectra obtained using the two-dimensional calculational model agree with the more definitive data obtained using the three-dimensional model within a factor of ∼5.