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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
Japanese researchers test detection devices at West Valley
Two research scientists from Japan’s Kyoto University and Kochi University of Technology visited the West Valley Demonstration Project in western New York state earlier this fall to test their novel radiation detectors, the Department of Energy’s Office of Environmental Management announced on November 19.
Technical Session
Thursday, May 19, 2022|8:00–9:45AM EDT|Pointview
Session Chair:
Michael L. Zerkle
Alternate Chair:
Adam G. Nelson
Session Organizer:
John D. Bess
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Thermal Neutron Scattering Law Evaluations for Zirconium Carbide and Critical Mass Calculations
J.L. Wormald (Naval Nuclear Laboratory), J.C. Holmes (Naval Nuclear Laboratory), M.L. Zerkle (Naval Nuclear Laboratory)
Paper
Spectral Indices Measurements for Neutron Data Validation in the Lead - Bismuth VENUS-F Fast Cores for MYRRHA
A. Kochetkov (SCK CEN), A. Krása (SCK CEN), N. Messaoudi (SCK CEN), G. Vittiglio (SCK CEN), J. Wagemans (SCK CEN)
Measurement of U-233 Sample Reactivity Worth in KUCA for Integral Validation of Nuclear Data
Tadafumi Sano (Kindai Univ.), Jun-ichi Hori (Kyoto Univ.), Yoshiyuki Takahashi (Kyoto Univ.), Kazushi Terada (Kyoto Univ.), Hiroshi Yashima (Kyoto Univ.), Takashi Kanda (Kindai Univ.), Hironobu Unesaki (Kyoto Univ.)
Development of a Model to Estimate Resuspension of Fission Products in an Integral Pressurized Water Reactor Containment Vessel
Rohan Biwalkar (Pittsburgh Technical), Iza Lantgios (Univ. Pittsburgh), Sola Talabi (Pittsburgh Technical), Katherine Hornbostel (Univ. Pittsburgh)
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