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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.
Yin-Pang Ma, Bau-Shei Pei, Wei-Keng Lin, Yih-Yun Hsu
Nuclear Technology | Volume 92 | Number 1 | October 1990 | Pages 134-140
Technical Paper | Development of Nuclear Gas Cleaning and Filtering Techniques / Heat Transfer and Fluid Flow | doi.org/10.13182/NT90-A34493
Articles are hosted by Taylor and Francis Online.
A physically based theoretical model of gas-liquid and steam-water two-phase flow in a horizontal tee-junction is developed. The model includes five independent equations: the mixture continuity equation, the vapor-phase continuity equation, the x direction momentum equation, the y direction momentum equation, and the energy equation. Any five unknown hydraulic parameters of the tee-junction can be solved in various ways, for virtually any choice of three well-posed boundary conditions. The uncertainty of the interfacial terms and the number of empirical constants that are used in the model are limited. The results of the calculations are compared with experimental data gathered from the literature. The comparison shows that the predictive ability of the model is reasonably good, except that the mass balance equation of the vapor phase is not suitable for some of the steam-water experimental data, and interfacial evaporation and condensation terms should be introduced into the model in the future.