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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.
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2023)
February 6–9, 2023
Amelia Island, FL|Omni Amelia Island Resort
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
Fusion Science and Technology
Belgium mulls life extension for more reactors
The Belgian government is exploring the idea of extending the operational life of its three oldest reactors by two years, a variety of news outlets are reporting.
Those reactors—Units 1 and 2 at the Doel facility and Unit 1 at Tihange, sporting a combined capacity of 1,852 MWe—were slated to be permanently shuttered in 2025 in keeping with the country’s nuclear phase-out policy.
Technical Session|Evolutionary and Innovative Advanced Technology Fuels (ATF)
Wednesday, October 12, 2022|1:30–3:10PM EDT|Salon A/B
Hyochan Kim (KAERI)
Jae Ho Yang (KAERI)
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Wrought FeCrAl Alloy (C26M) Cladding Behavior During Burst Experiments and Performance Under LOCA Conditions
R.T. Sweet (ORNL), C.P. Massey (ORNL), S.B. Bell (Univ. Tennessee., Knoxville), K.A. Kane (ORNL)
Limiting Degradation Mechanisms for High-Temperature Oxidation Resistance of Promising ATF Cladding Solutions
Martin Steinbrueck (Karlsruhe Institute of Technology), Mirco Grosse (Karlsruhe Institute for Technology), Chongchong Tang (Karlsruhe Institute of Technology), Juri Stuckert (Karlsruhe Institute of Technology)
Use of Chromium Coating to Provide Protection of Zirconium Cladding at DNB Conditions
Zeses Karoutas (Westinghouse Electric Co.), Dave Mitchell (Westinghouse Electric Co.), Yixing Sung (Westinghouse Electric Co.), Guoqiang Wang (Westinghouse Electric Co.), William A. Byers (Westinghouse Electric Co.), Michael Conner (Westinghouse Electric Co.)
Assessment of Thin Tube of Alumina-Forming Duplex Stainless Steels (ADSS) as Accident Tolerant Fuel Cladding Materials for Light Water Reactors
Chaewon Kim (KAIST), Woong Heo (KAIST), Changheui Jang (KAIST), Sung Yong Lee (KEPCO Nuclear Fuel), Hun Jang (KEPCO Nuclear Fuel), Seungjae Lee (KEPCO Nuclear Fuel)
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