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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
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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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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.
Michael Drevlak
Fusion Science and Technology | Volume 33 | Number 2 | March 1998 | Pages 106-117
Technical Paper | doi.org/10.13182/FST98-A21
Articles are hosted by Taylor and Francis Online.
A method for finding a set of modular, poloidally closed stellarator coils confining a plasma in a given equilibrium configuration is described. The proposed technique performs a direct nonlinear optimization of the coil shapes with respect both to the desired structure of the magnetic field and to geometric constraints required by the fabrication process of the coils. This is in contrast to the method employed successfully for the design of the coil system of experiment W7-X, which divides the minimization of the field error and the adjustment of the geometric coil properties into consecutive steps. The viability of the new method is exemplified by two alternative coil designs for the plasma configuration of W7-X, offering more space inside the coils for installation of the divertor system or a blanket. The results are compared with the original coil configuration designed for W7-X.