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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Fusion Science and Technology
Latest News
Framatome signs contracts with Sizewell C
French nuclear developer Framatome is slated to deliver key equipment for Sizewell C Ltd.’s two large reactors planned for the United Kingdom’s Suffolk coast.
The agreement, reportedly worth multiple billions of euros, was announced this week and will involve Framatome from the design phase until commissioning. The company also agreed to a long-term fuel supply deal. Framatome is 80.5 percent owned by France’s EDF and 19.5 percent owned by Mitsubishi Heavy Industries.
Jonathan Coburn, Mohamed Bourham
Fusion Science and Technology | Volume 72 | Number 4 | November 2017 | Pages 692-698
Technical Note | doi.org/10.1080/15361055.2017.1352426
Articles are hosted by Taylor and Francis Online.
Innovative materials are investigated using a simulated electrothermal (ET) plasma to characterize erosion characteristics under ITER-relevant off-normal conditions. The tungsten alternatives investigated are mono-crystalline silicon carbides and MAX Phase ceramics. Preliminary code simulations using the ETFLOW plasma code are presented to assess erosive behavior in preparation for future experiments at ORNL’s electrothermal high heat flux experiment and the DiMES experiments for induced disruption on the DIII-D tokamak. Results indicate that erosion properties for SiC and two commercially available MAX Phases, Ti3SiC2 and Ti2AlC, compare well with tungsten and other ITER relevant components. A material-specific ablation constant, measured as total mass removed per incident heat flux per second, serves as a means for directly comparing erosion properties. Tungsten possesses the highest ablation constant value when compared to carbon, beryllium and the alternative materials α-6H SiC, Ti3SiC2, and Ti2AlC. The ablation thickness, calculated from the ablation constant and the specific density of the material, provides a comparison of surface thickness lost during a given off-normal event. Carbon (4.25 cm3/MJ) and tungsten (5.98 cm3/MJ) possess the lowest values. The alternative materials Ti3SiC2 (7.32 cm3/MJ) and α-6H SiC (8.44 cm3/MJ) exhibit the next best values, with Ti2AlC being the least effective (9.35 cm3/MJ). SiC shows the best vapor shielding efficiency of the three alternative materials, with Ti3SiC2 and Ti2AlC giving similar efficiencies. Taking into account vapor shielding effects using both opacity and fractional models, SiC exhibits the best ablation characteristics of the three materials in terms of thickness loss, with Ti3SiC2 giving similar results and overall appearing the superior of the two MAX Phases.
