ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
May 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Webinar: MC&A and safety in advanced reactors in focus
Towell
Russell
Prasad
The American Nuclear Society’s Nuclear Nonproliferation Policy Division recently hosted a webinar on updating material control and accounting (MC&A) and security regulations for the evolving field of advanced reactors.
Moderator Shikha Prasad (CEO, Srijan LLC) was joined by two presenters, John Russell and Lester Towell, who looked at how regulations that were historically developed for traditional light water reactors will apply to the next generation of nuclear technology and what changes need to be made.
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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