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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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Latest News
Senate committee hears from energy secretary nominee Chris Wright
Wright
Chris Wright, president-elect Trump’s pick to lead the U.S. Department of Energy, spent hours today fielding questions from members of the U.S. Senate’s committee on Energy and Natural Resources.
During the hearing, Wright—who’s spent most of his career in fossil fuels—made comments in support of nuclear energy and efforts to expand domestic generation in the near future. Asked what actions he would take as energy secretary to improve the development and deployment of SMRs, Wright said: “It’s a big challenge, and I’m new to government, so I can’t list off the five levers I can pull. But (I’ve been in discussions) about how to make it easier to research, to invest, to build things. The DOE has land at some of its facilities that can be helpful in this regard.”
Hyun Chul Lee, Chang Hyo Kim
Nuclear Science and Engineering | Volume 138 | Number 2 | June 2001 | Pages 192-204
Technical Paper | doi.org/10.13182/NSE01-A2209
Articles are hosted by Taylor and Francis Online.
This paper demonstrates that the analytic nodal method (ANM) solution to two-group (2-G) diffusion equations can be formulated in the same way as the nodal expansion method (NEM) solution, and thereby, the two most popular transverse integrated nodal method formulations can be integrated into a unified nodal method (UNM) formulation. For this purpose, the analytic solution, i.e., the combined homogeneous and particular solution, of transverse-integrated one-dimensional, 2-G diffusion equations is represented by an expansion of analytic basis functions while the expansion coefficients are obtained in the same way as the NEM. The advantages of the UNM formulation are then discussed. It is a stable method in itself so that it does not require approximate schemes to avoid the instability at the near-critical nodes. Because it does not introduce any approximate scheme in conjunction with the stability questions at the near-critical nodes, it is more accurate than the conventional ANM formulation in the case where the latter needs to introduce approximations. It is readily incorporated into a number of existing NEM production codes. These advantages are demonstrated in terms of numerical solutions of Nuclear Energy Agency Committee on Reactor Physics pressurized water reactor benchmark problems.