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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
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Fusion Science and Technology
Latest News
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
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.