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Division Spotlight
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.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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 Science and Engineering
February 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Ontario eyes new nuclear development
A 1,300-acre site left undeveloped on the shores of Lake Ontario four decades ago could see new life as the home to a large nuclear facility.
Mazhyn Skakov, Gainiya Zhanbolatova, Arman Miniyazov, Timur Tulenbergenov, Igor Sokolov, Yerzhan Sapatayev, Yernat Kozhakhmetov, Olga Bukina
Fusion Science and Technology | Volume 77 | Number 1 | January 2021 | Pages 57-66
Technical Paper | doi.org/10.1080/15361055.2020.1843885
Articles are hosted by Taylor and Francis Online.
This paper presents the results of a study on impact of high-power heat load and tungsten (W) surface carbidization on its structural-phase composition and physical-mechanical properties. In this regard, carbidization of a W surface was carried out by means of beam-plasma discharge in a simulation machine with plasma-beam installation. Certain data were obtained regarding temperature in control points of studied samples and temperature distribution throughout the monoblock element, made as a rectangle with an orifice for a cooling path, placed in a fusion reactor divertor. The paper demonstrates that changes in heat load power have an impact on microhardness, roughness, atomization of the carbidized W surface, and phase formation processes. It was established that a heat load q = 10 MW/m2 has very little effect on the elemental composition of the surface and structural-phase composition of W samples with a carbidized layer. Growth of thermal load up to q = 20 MW/m2 leads to a noticeable transformation of tungsten monocarbide (WC) into tungsten semicarbide (W2C) and cracking of the W sample surface.
