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 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
Latest Magazine Issues
Jun 2026
Jan 2026
2026
Latest Journal Issues
Nuclear Science and Engineering
July 2026
Nuclear Technology
June 2026
Fusion Science and Technology
May 2026
Latest News
MIT Maritime Consortium wins ABS approval
Maritime classification and certification organization the American Bureau of Shipping has granted its approval in principle (AIP) for the integration of a nuclear reactor into a cargo vessel propulsion system, as developed by the Massachusetts Institute of Technology Maritime Consortium. This is the first AIP to be granted to a technology developed through the consortium, which includes founding members MIT, HD Korea Shipbuilding & Offshore Engineering, and Capital Maritime Group.
Technical Session|Experimental Thermal Hydraulics
Wednesday, August 23, 2023|10:45AM–12:25PM EDT|Cardozo
Session Chair:
Guanyu Su (UCB)
Session Organizer:
Bao-Wen Yang (DEDQ)
To access paper attachments, you must be logged in and registered for the meeting.
Register NowLog In
Experimental Investigations of Material-Conjugated Subcooled Flow Boiling
10:45–11:05AM EDT
Mingfu He (Univ. New Mexico), Minghui Chen (Univ. New Mexico)
Paper
The Effect of Time Varying Axial Power Shape on Transient Critical Power Performance of BWR Fuel
11:05–11:25AM EDT
B. Ward (Global Nuclear Fuel Americas), S. Oh (Global Nuclear Fuel Americas), J. Andersen (Global Nuclear Fuel Americas), C. Heck (Global Nuclear Fuel Americas), D. Rock (Global Nuclear Fuel Americas), M. Sugawara (Global Nuclear Fuel Americas), J. Lamy (Global Nuclear Fuel Americas)
Presentation Slides (Visible to Attendees)
Steady-State and Power Transient Critical Heat Flux Experiments of FeCrAl and Zircaloy Claddings Under Saturated Pool Boiling
11:25–11:45AM EDT
Experimental Research About Corrosion Effect on Boiling Heat Transfer Performance of Plate-Type Samples with Micro-Structures
11:45AM–12:05PM EDT
Wei Xu (Shanghai Jiao Tong Univ.), Xiaojing Liu (Shanghai Jiao Tong Univ.), Kun Ouyang (Shanghai Jiao Tong Univ.), Xiaoqiang He (Nuclear Power Institute of China)
Presentation Video (Visible to Attendees) — Wei Xu