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Conference Spotlight
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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
Dec 2025
Jul 2025
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Nuclear Science and Engineering
January 2026
Nuclear Technology
December 2025
Fusion Science and Technology
November 2025
Latest News
What’s the most difficult question you’ve been asked as a maintenance instructor?
Blye Widmar
"Where are the prints?!"
This was the final question in an onslaught of verbal feedback, comments, and critiques I received from my students back in 2019. I had two years of instructor experience and was teaching a class that had been meticulously rehearsed in preparation for an accreditation visit. I knew the training material well and transferred that knowledge effectively enough for all the students to pass the class. As we wrapped up, I asked the students how they felt about my first big system-level class, and they did not hold back.
“Why was the exam from memory when we don’t work from memory in the plant?” “Why didn’t we refer to the vendor documents?” “Why didn’t we practice more on the mock-up?” And so on.
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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