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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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. N. Blomquist, E. E. Lewis
Nuclear Science and Engineering | Volume 73 | Number 2 | February 1980 | Pages 125-139
Technical Paper | doi.org/10.13182/NSE80-A18693
Articles are hosted by Taylor and Francis Online.
The variational formulation of the even-parity form of the within-group neutron transport equation is generalized to include complex trial functions. The introduction of transverse leakage effects through the buckling term exp(iB·r) leads, in general, to a coupled set of Euler equations for the real and imaginary even-parity flux components. The coupling between real and imaginary flux components is retained in both discrete-ordinates and finite element angular approximations. Employment of the spherical harmonics approximations in angle, however, leads to an uncoupled set of Euler equations if an appropriate choice of axes is made. Hence, a rigorous buckling treatment of third-dimensional leakage can be incorporated into two-dimensional transport computations without solving for the imaginary flux component. The foregoing spherical harmonic formulation is combined with finite element discretization in space in the multigroup criticality code FESH. One- and multigroup results are presented to demonstrate the elimination of ray effects and to examine the errors introduced by the DB2 leakage correction used in conventional transport calculations.