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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
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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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
R. Toschi
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 201-205
Next-Generation Device | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A40046
Articles are hosted by Taylor and Francis Online.
The European strategy envisages at least one major plasma device between the present generation machines such as JET and the Fusion Demonstration Reactor (DEMO). The European Community has decided to start the definition of this device, designated NET (Next European Torus), to be the focal point and to provide guidance for the current fusion effort particularly the technology programme. NET aims to produce a plasma with reactor-like parameters (i.e. full ignition, extended burn pulse and adequate power density) and with machine parameters and configuration which could be safely extrapolated to DEMO. As far as possible, NET will adopt reactor relevant technologies and be capable of performing engineering testing for the development of the DEMO blanket/first wall. The essential objectives of the programme can be achieved after three quarters of a full power year but provisions are made for continuing the operation up to almost three full power years. A reference parameter set is now being defined together with the main options for the configuration and the principal components. Present uncertainties in the physics data base are leading us to choose a set of parameters which offer considerable safety margins in the physics but, the configuration is being simultaneously optimized for maximum compactness. The degree of extrapolation in scale, performance and operating conditions from NET to DEMO appears to be acceptable. However, the DEMO should operate as a Component Test Reactor to complete the development of nuclear components capable of withstanding high neutron fluence. The definition of the reference parameter set will be followed by the predesign of NET and an associated Technology Programme oriented towards the needs of the device will be implemented; in 1988 the data base on physics and technology should be sufficient to enter into the detailed design leading to a decision on construction in 1992.