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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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
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
IAEA to help monitor plastic pollution in the Galapagos Islands
The International Atomic Energy Agency announced that its Nuclear Technology for Controlling Plastic Pollution (NUTEC Plastics) initiative has partnered with Ecuador’s Oceanographic Institute of the Navy (INOCAR) and Polytechnic School of the Coast (ESPOL) to build microplastic monitoring and analytical capacity to address the growing threat of marine microplastic pollution in the Galapagos Islands.
Thijs Wijnands, Gilles Martin
Fusion Science and Technology | Volume 32 | Number 3 | November 1997 | Pages 471-486
Technical Paper | doi.org/10.13182/FST97-A9
Articles are hosted by Taylor and Francis Online.
The first results on plasma control with the new plasma control system of Tore Supra are described. The system has been especially designed for long-pulse operation: Plasmas are controlled by reference signals, which can be varied in real time by using diagnostic measurements. On-line determination of the global plasma equilibrium has enabled new operation scenarios in which both the power from the poloidal field generators and the total lower-hybrid (LH) power are used to control the plasma. Experiments with feedback control of the safety factor on the plasma boundary, control of the LH-driven current, control of the flux on the plasma boundary, and control of the internal inductance are demonstrated. Finally, future modifications to the system, aimed at controlling the current profile during long-pulse operation, are discussed.
