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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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 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.”
Askar A. Gubaidullin, Bal Raj Sehgal
Nuclear Technology | Volume 138 | Number 1 | April 2002 | Pages 90-92
Technical Note | Thermal Hydraulics | doi.org/10.13182/NT02-A3280
Articles are hosted by Taylor and Francis Online.
A semiempirical correlation for an estimate of crust thickness in a molten pool is presented and validated against published experimental data. The proposed correlation between the dimensionless crust thickness and the Biot and the Prandtl numbers has been developed as [overbar]* = 14.49BiPr -0.074. A scaling methodology is discussed to analyze the thermal resistance of the crust. The results are of interest for the corium melt coolability in a postulated severe accident scenario in a light water reactor.