ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Constellation seeks rezone for property adjacent to Illinois plant
While no development details have been released, Constellation is asking to rezone 658.8 acres of land it owns around the Byron nuclear plant in Illinois for possible long-term use.
Han Eol Park, Seok Bin Seo, In Cheol Bang (UNIST)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 479-484
Nu-HOPE (Nuclear-Highly Optimized Prandtl number Experiment facility) is a newly built facility in UNIST to simulate molten salt reactor. Due to the high-temperature corrosion and toxicity issue, the heat transfer phenomena of molten salt are studied under similarity technique with high-Prandtl number simulant fluid. 12-meter-high Nu-HOPE was designed for the study of both natural and forced circulation of high-Prandtl number fluid. Experimental results of natural and forced circulation can give the evaluation of heat transfer characteristics and fluid stability model for the simulant molten salt. In this paper, design of Nu-HOPE based on numerical approach to developing heat transfer model of high-Prandtl number fluid is suggested.