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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Fusion Science and Technology
Latest News
College students help develop waste-measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
P. W. Humrickhouse, P. Calderoni, B. J. Merrill
Fusion Science and Technology | Volume 60 | Number 4 | November 2011 | Pages 1564-1567
Interaction with Materials | Proceedings of the Ninth International Conference on Tritium Science and Technology (Part 2) | doi.org/10.13182/FST11-A12732
Articles are hosted by Taylor and Francis Online.
A number of additions have been made to the computational fluid dynamics (CFD) code Fluent in order to model hydrogen permeation. In addition to fluid dynamics, Fluent solves for heat transfer in coupled solid and fluid regions, and solves advection-diffusion equations for scalar quantities such as hydrogen concentration. The latter have been modified with additional code to satisfy Sievert's Law at solid-fluid interfaces and allow for temperature dependent diffusivity and permeability.The method has been employed to model the Tritium Heat Exchanger (THX) experiment at INL, which investigates hydrogen permeation in helium and candidate structural materials for high temperature gas reactor heat exchangers. The Arrhenius law parameters used in Fluent for Inconel 617 are initially determined via a simplified analytical method, and the resulting model predictions compare favorably with experiment data.