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Division Spotlight
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.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
R. P. Smedley-Stevenson
Nuclear Science and Engineering | Volume 142 | Number 1 | September 2002 | Pages 75-84
Technical Note | doi.org/10.13182/NSE02-A2289
Articles are hosted by Taylor and Francis Online.
This technical note compares the results for streaming along a single-ray direction from linear discontinuous finite element discretizations of the transport equation using both Galerkin and Petrov-Galerkin weight functions. The utility of a slope limiter to remove extrema from the transport solution is investigated as an alternative to mass lumping of the removal operator; the latter procedure introduces significant numerical diffusion and can destroy the fidelity of the solution. Results are presented for single-ray propagation in slab geometry and two-dimensional planar geometry.