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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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Fusion Science and Technology
Latest News
The JT-60SA project
JT-60SA (Japan Torus-60 Super Advanced) is the world’s largest superconducting tokamak device. Its goal is the earlier realization of fusion energy (see Fig. 1). Fusion is the energy that powers the Sun, and just 1 gram of deuterium-tritium (D-T) fuel produces enormous energy—the equivalent of 8 tons of crude oil.
Last fall, the JT-60SA project announced an important milestone: the achievement of the tokamak’s first plasma. This article describes the objectives of the JT-60SA project, achievements in the operation campaign for the first plasma, and next steps.
J. S. Jaquez, A. Nikroo, N. A. Hein, W. Sweet
Fusion Science and Technology | Volume 63 | Number 2 | March-April 2013 | Pages 226-231
Technical Paper | Selected papers from 20th Target Fabrication Meeting, May 20-24, 2012, Santa Fe, NM, Guest Editor: Robert C. Cook | doi.org/10.13182/FST13-A16342
Articles are hosted by Taylor and Francis Online.
Simulations of ignition-scale hohlraums show that the addition to the hohlraum of a submicron-thick Au/B interior liner containing [approximately]20 to 40 at. % B likely reduces laser backscatter by reducing the stimulated Brillouin scattering. By reducing the backscatter, the amount of energy available to compress the inertial confinement fusion capsule is increased while the likelihood of laser damage at National Ignition Facility (NIF) is minimized. A specialized magnetron cosputtering process is used to fabricate Au/B liners between 0.6 and 1.2 m for use on hohlraums shot at NIF to the atomic concentrations of 20 to 40 at. % B. We will discuss recent process improvements, such as LabVIEW process automation, in situ rate and thickness measurements, and optimized coating setup, all of which have increased the hohlraum yield and hohlraum throughput as well as increased control and confidence in Au/B liner thickness and B concentration uniformity and reproducibility. We will also discuss effects of various leaching mechanisms affecting B concentration in the Au/B liner.