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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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Nuclear Science and Engineering
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Nuclear Technology
Fusion Science and Technology
Latest News
Pacific Fusion predicts “1,000-fold leap” in performance, net facility gain by 2030
Inertial fusion energy (IFE) developer Pacific Fusion, based in Fremont, Calif., announced this morning that it is on target to achieve net facility gain—more fusion energy out than all energy stored in the system—with a demonstration system by 2030, and backs the claim with a technical paper published yesterday on arXiv: “Affordable, manageable, practical, and scalable (AMPS) high-yield and high-gain inertial fusion.”
Tatsuhiko Uda, Hajime Iba, Hiroyuki Tsuchiya
Nuclear Technology | Volume 73 | Number 1 | April 1986 | Pages 109-115
Technical Paper | Material | doi.org/10.13182/NT86-A16207
Articles are hosted by Taylor and Francis Online.
Melt refining as a means of uranium decontamination of metallic wastes was examined. Samples of mild steel, contaminated with uranium, were melted by adding SiO2-CaO-Al2O3 ternary system fluxes. Various melting temperatures and times were used, and the uranium concentrations in the resulting ingots were determined. Flux, and hence slag, composition was found to influence the level of decontamination, but melting temperature and time had little effect. Using the most effective flux composition (10 SiO2-50 CaO-40 Al2O3), uranium concentration was lowered from a contamination level of 500 to 0.027 ppm, a value nearly that of the initial steel before contamination. When the ionic character of slag was defined using basicity [the mole ratio of basic oxide (CaO) to acidic oxide (SiO2 + Al2O3)], the optimum decontamination value was found near a basicity of 1.6. The slag anions of silicate or aluminate seemed to affect the uranium decontamination.