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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Vogtle-3 shuts down for valve issue
One of the new Vogtle units in Georgia was shut down unexpectedly on Monday last week for a valve issue that has since been investigated and repaired. According to multiple local news outlets, Georgia Power reported on July 17 that Unit 3 was back in service.
Southern Company spokesperson Jacob Hawkins confirmed that Vogtle-3 went off line at 9:25 p.m. local time on July 8 “due to lowering water levels in the steam generators caused by a valve issue on one of the three main feedwater pumps.”
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.