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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
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
Nov 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
NRC okays construction permits for Hermes 2 test facility
The Nuclear Regulatory Commission announced yesterday that it has directed staff to issue construction permits to Kairos Power for the company's proposed Hermes 2 nonpower test reactor facility to be built at the Heritage Center Industrial Park in Oak Ridge, Tenn. The permits authorize Kairos to build a facility with two 35-MWt test reactors that would use molten salt to cool the reactor cores.
Technical Session|Sponsored by OPD
Tuesday, June 13, 2023|10:00–11:45AM EDT|Tennessee
Session Chair:
Temi Adeyeye (NuScale)
Alternate Chair:
Timothy M. Crook (Blue Wave AI Labs)
Session Organizer:
William N. Mann (ANL)
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Evaluating Scaling Effects of Steam Condensation Physics-Based Model for Small Modular Reactor
10:00–10:20AM EDT
Palash K. Bhowmik (INL), Joshua P. Schlegel (Missouri Univ. Science and Technology), Piyush Sabharwall (INL)
Paper
Accelerating Nuclear Fuels and Materials Qualification by Multi-Level Irradiation Experiment Campaign
10:20–10:40AM EDT
Palash K. Bhowmik (INL), Piyush Sabharwall (INL), Brenden Heidrich (INL), Richard H. Howard (ORNL)
Effect of Fuel-Moderator Porosity in Advanced HTGR Designs on the Depressurized Loss of Forced Convection and Compressor Power Requirements
10:40–11:00AM EDT
John Matulis (Purdue), Hitesh Bindra (Purdue)
Damage Assessment of Advanced High Temperature Fluid Reactor Piping System with Guided Wave Ultrasonics
11:00–11:20AM EDT
Chenxi Xu (Univ. Illinois, Chicago), Matthew Daly (Univ. Illinois, Chicago), Alexander Heifetz (ANL), Derek Kultgen (ANL), Didem Ozevin (Univ. Illinois, Chicago)
Transient Modelling of HTGR Thermal Load Follow in Modelica
11:20–11:40AM EDT
Aidan Rigby (Univ. Wisconsin, Madison), Ben Lindley (Univ. Wisconsin, Madison), Daniel Mikkelson (INL)
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