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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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.”
F.M.G. Wong, N.A. Mitchell, T. Kato, H. Nakajima, R. Randall, M. Morra
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 815-821
Superconducting Magnets and Joints | doi.org/10.13182/FST98-A11963714
Articles are hosted by Taylor and Francis Online.
Incoloy 908, an iron-nickel base superalloy that was developed as a Nb3Sn jacket material for Cable-In-Conduit Conductors, has been selected as the jacket material for the International Thermonuclear Experimental Reactor (ITER) Toroidal Field (TF) and Central Solenoid (CS) coils. It has a coefficient of expansion matching Nb3Sn (to minimise Jc and Tc degradation due to differential contraction after the reaction heat treatment). The alloy exhibits a characteristic of iron-nickel base superalloys: oxygen embrittlement along grain boundaries as a result of heating in an oxygen atmosphere when tensile surface stresses are present. For applications using Incoloy 908, techniques are required to control levels of either oxygen or tensile surface stresses during heat treatment. R & D results performed to develop and qualify such techniques for industrial applications are presented. The work has concentrated on establishing the lowest achievable oxygen levels inside the cable space during the reaction heat treatment and determining the conditions that can be tolerated inside and outside the jacket before SAGBO occurs. The results were applied in the ITER Model Coil programmes, in which about 5.5 km of conductor have been successfully heat treated.