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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
Meeting Spotlight
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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Amir Ali, Edward Blandford, Youho Lee (Univ of New Mexico), Khalid Hattar (SNL), Hyun-Gil Kim, Dong Jun Park (KAERI)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 428-439
The concept of coating the currently used nuclear fuel cladding (zirconium-based alloy) with an oxidation preventive layer could be a solution to suppress undesirable fast reaction kinetics with high-temperature steam. Critical Heat Flux (CHF) is a thermal-hydraulic performance parameter to investigate for these new cladding concepts including Cr-coated Zirc-based cladding. The exposure of coated Zirc-based cladding for an extensive period inside the reactor to severe conditions of high pressure and temperature, water chemistry, and irradiation environment could result in structure and property changes. These changes would have an impact on the heat transfer performance parameters including CHF. Surface wettability analysis, including contact angle (?) and surface roughness (Ra), are simple surface measurements used in the literature to predict changes in the pool boiling heat transfer coefficient and CHF. This work presents the effects of ion irradiation on surface wettability measurements and predicted pool boiling CHF for bare Zirc-4, and multiple Cr-coated Zirc-based samples of different coating thicknesses (5 - 30 ?m). The Scanning Electron Microscope (SEM) images show no significant surface damages due to ion irradiation. The ion irradiation shows no effects on the measured surface roughness for all samples. Results show that decreasing the Cr-coating thickness results in a higher surface wettability pre- and post- ion irradiation. The irradiated Cr-coated surfaces have higher measured contact angle compared to the unirradiated surfaces. The unpolished coated Zirc samples have larger measured surface roughness compared to the polished surfaces pre- and post- ion irradiation. The predicted pool boiling CHF using the contact angle measurements implemented in Kandlikar model for unirradiated samples is higher than those for irradiated samples.