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Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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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
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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
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.”
T.V. Kulsartov, Y.V. Chikhray, I.L. Tazhibaeva, V.P. Shestakov
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 919-923
Plasma Facing Components Technology (Poster Session) | doi.org/10.13182/FST98-A11963730
Articles are hosted by Taylor and Francis Online.
Be-copper alloy duplex structures are planed to be used as the structural material of the first wall for ITER. CuCr1Zr0.1 copper alloy is one of the prospective components of such structures. To ensure safety and to solve ecological problems concerning fusion reactor operation it is necessary to have estimations of tritium inventory in the copper alloy CuCr1Zr0.1 and in Be-copper alloy duplex structures.
In this work the results of the following experiments on determination of hydrogen permeation parameters are presented:
• Investigation of hydrogen permeation for beryllium-copper duplex structure. Experiments were carried out in the temperature range from 873 K to 1023 K, at input hydrogen pressures between 102 Pa and 103 Pa.
• Investigation of hydrogen permeation for copper alloy CuCr1Zr0.1 in the temperature range from 723 K to 973 K, at input pressures of hydrogen between 102 and 103 Pa and for samples with different thickness.
