ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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.
2021 ANS Virtual Annual Meeting
June 14–16, 2021
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
How the NRC modernized its digital I&C infrastructure and where it goes from here
The Nuclear Regulatory Commissiona first formally developed infrastructure for the review of digital instrumentation and control (I&C) systems in the 1990s. Although the current fleet of nuclear power plants in the United States was originally designed and constructed with analog systems, the U.S. nuclear industry has for more than 30 years been working to upgrade these older systems with modern digital equipment.
Friday, April 9, 2021|10:00–11:30AM (11:00AM–12:30PM EDT)
Yuqiao Joy Fan (NCSU)
Edward Chen (NCSU)
Halil Ibrahim San (NCSU)
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Pressure Distribution in Free and Impinging Jets for High-Energy Piping Systems
Zhengting Quan (Purdue University), Ran Kong (Purdue University), Seungjin Kim (Purdue University), Mamoru Ishii (Purdue University)
Thermal Decomposition of Carbonates as a Passive Cooling Mechanism for Molten Salt Reactors
Christopher T. Forsyth (University of California Berkeley)
Improvements in Bypass flow Analysis Using CORONA Code
Dylan D. Ohrt (University of Texas Permian Basin)
Design of a Sodium Heat Pipe Experimental Setup for the Special Purpose Nuclear Reactor
Pei-Hsun Huang (University of Michigan), Taehwan Ahn (University of Michigan), Annalisa Manera (University of Michigan), Victor Petrov (University of Michigan)
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