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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
2022 ANS Annual Meeting
June 12–16, 2022
Anaheim, CA|Anaheim Hilton
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!
Latest Magazine Issues
Dec 2021
Jul 2021
Latest Journal Issues
Nuclear Science and Engineering
December 2021
Nuclear Technology
Fusion Science and Technology
November 2021
Latest News
Latest delay to Vogtle project may not be the last
Georgia Power has revised the projected commercial operation dates for Vogtle-3 and -4 a total of four times this year—most recently in October—but some experts are saying that at least one more delay is probable.
Technical Session
Friday, April 9, 2021|10:00–11:30AM (11:00AM–12:30PM EDT)
Session Chair:
Yuqiao Joy Fan (NCSU)
Alternate Chair:
Ishita Trivedi
Session Organizer:
Edward Chen (NCSU)
Track Organizer:
Session Producers:
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)
Summary
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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