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Division Spotlight
Thermal Hydraulics
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.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2021)
February 9–11, 2021
Virtual Meeting
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
Jan 2021
Jul 2020
Latest Journal Issues
Nuclear Science and Engineering
February 2021
Nuclear Technology
January 2021
Fusion Science and Technology
November 2020
Latest News
Former NRC chairs issue vaccine timeline recommendation to CDC
Five former chairmen of the U.S. Nuclear Regulatory Commission—Stephen Burns, Allison Macfarlane, Nils Diaz, Richard Meserve, and Dale Klein—signed a letter to José Romero, Arkansas health secretary and chair of the Centers for Disease Control and Prevention (CDC) immunization advisory committee, requesting that the advisory committee update its recommendation for COVID-19 vaccine allocation guidance for the energy workforce (including nuclear energy workers).
Currently, the CDC has four phases for the COVID-19 vaccine rollout. Those phases are numbered:
Technical Session|Sponsored by OPD
Thursday, November 19, 2020|9:00–10:45AM (10:00–11:45AM EST)
Session Chair:
N. Dianne B. Ezell (ORNL)
Alternate Chair:
W. Neal Mann (The University of Texas at Austin)
Session Organizer:
Staff Producer:
Paul LaTour (American Nuclear Society)
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TRANSFORM - A Vision for Modern Advanced Reactor System-Level Modeling and Simulation Using Modelica
Michael S. Greenwood (Oak Ridge National Laboratory)
Summary
Gear Test Assembly - Testing Gears and Bearings in Liquid Sodium
Edward Kent (Argonne National Laboratory), Henry Belch (Argonne National Laboratory), Sasan Bakhtiari (Argonne National Laboratory), H.T. Chien (Argonne National Laboratory), Chris Grandy (Argonne National Laboratory)
SMART Natural Circulation Long Term Cooling Performance Analysis for the Extended Design Basis Accidents using MARS-KS
Youn Shil Kim (Environment & Energy Technology, Inc.), Sunghwan Bae (Environment & Energy Technology, Inc), Nhan H. Hoang (Environment & Energy Technology, Inc), S.K. Sim (Environment & Energy Technology, Inc)
Presentation Video
Generalized Python Tool for Thermal Hydraulics Core Analysis of Advanced Reactors
Sierra Tutwiler (Virginia Commonwealth University), Lane B. Carasik (Virginia Commonwealth University)
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