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.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Jan 2026
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
February 2026
Nuclear Technology
December 2025
Fusion Science and Technology
November 2025
Latest News
Kairos Power finalizes contract on HALEU for Hermes
Kairos Power has finalized a contract with the Department of Energy to receive high-assay low-enriched uranium (HALEU) from the agency for the company’s Hermes low-power demonstration reactor, currently under construction in Oak Ridge, Tenn.
In partnership with Los Alamos National Laboratory, Kairos intends to use the DOE-provided material to produce HALEU TRISO fuel pebbles for Hermes. The company views the Hermes test reactor and the fuel fabrication program as crucial to the eventual success of its power-producing Hermes 2 demonstration plant, also to be sited in Oak Ridge, and future commercial fluoride salt–cooled high-temperature reactors.
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)
To access paper attachments, you must be logged in and registered for the meeting.
Register NowLog In
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)
To join the conversation, you must be logged in and registered for the meeting.