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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.
Hikaru Hiruta, Dmitriy Y. Anistratov
Nuclear Science and Engineering | Volume 154 | Number 3 | November 2006 | Pages 328-352
Technical Paper | doi.org/10.13182/NSE06-A2637
Articles are hosted by Taylor and Francis Online.
In this paper, we develop a homogenization methodology for the two-dimensional low-order quasi-diffusion equations for full-core reactor calculations that is based on a family of spatially consistent coarse-mesh discretization methods. The coarse-mesh solution generated by these methods preserves a number of spatial moments of the fine-mesh transport solution over each assembly. The proposed method reproduces accurately the complicated large-scale behavior of the transport solution within assemblies. To demonstrate the performance of the developed methodology, we present the numerical results of several test problems that simulate mixed-oxide-uranium and assembly-reflector interfacial effects.