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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
2023 ANS Winter Conference and Expo
November 12–15, 2023
Washington, D.C.|Washington Hilton
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!
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Nuclear Science and Engineering
Fusion Science and Technology
Offshore nuclear power concept under development by BWXT and Crowley
BWX Technologies is teaming with Crowley, a global shipping and energy supply chain company, under a memorandum of understanding to develop a ship with an onboard microreactor that could deliver power to users on shore via buoyed power cables. The concept, announced by both companies on September 20, is envisioned as a zero-carbon energy option for defense and disaster needs.
Panel and Technical Session|Lightning Talks
Saturday, April 15, 2023|10:15–11:35AM EDT|Student Union 262A
Lance M. Drouet
Matthew McMillan (Univ. Tennessee, Knoxville)
This session is sponsored by ARPA-E.
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Wavelength-Resolved Thermoluminescence for Scintillator Development
Rebecca Lalk (Univ. Tennessee, Knoxville), Yauhen Tratsiak (Univ. Tennessee, Knoxville), Luis Stand (Univ. Tennessee, Knoxville), Charles L. Melcher (Univ. Tennessee, Knoxville), Mariya Zhuravleva (Univ. Tennessee, Knoxville)
Simulated Nuclear Detection Algorithm Adaptation: Spectral Comparison Ratios
Andrew Sanchez (US Military Academy)
Neutronics Analysis of Molten Uranium Breeder Reactor with a Code-to-Code Verification
Christian M. Pochron (Virginia Commonwealth Univ.), Zeyun Wu (Virginia Commonwealth Univ.), Neal L. Mann (Neal Mann & Associates), Mihai (Mike) G. Pop (AREVA NP, Inc.)
Development and Evaluation of Parallel Simulated Annealing Algorithm for Reactor Core Optimization Problems
Robert J. Mikouchi-Lopez (NCSU), Gregory K. Delipei (NCSU), Jason Hou (NCSU)
An Introduction to Quantitative Compton Imaging
Jonathan T. Mitchell (Univ. Tennessee, Knoxville), Michael J. Liesenfelt (Univ. Tennessee, Knoxville), Blake Montz (Univ. Tennessee, Knoxville), Jason P. Hayward (Univ. Tennessee, Knoxville), Jeff Preston (Y-12 National Security Complex), Ramkumar Venkataraman (ORNL), Kyle Schmitt (ORNL), Klaus Ziock (ORNL)
Analysis of Post-CHF Heat Transfer for Downward Vertical Boiling in a Square Channel
Nataly R. Panczyk (Univ. Illinois, Urbana-Champaign), Ethan H. Nicolls (Univ. Illinois, Urbana-Champaign), Joseph L. Bottini (Univ. Illinois, Urbana-Champaign), Caleb S. Brooks (Univ. Illinois, Urbana-Champaign)
Feasibility and Mechanics of SiC Flow for Fabrication of Containment Structures
Katie Karl (Univ. Tennessee, Knoxville), Caen K. Ang (Ultra Safe Nuclear Corp.), Christopher B. Shaver (Univ. Tennessee, Knoxville)
Thermal Micromechanical Tensile Testing Technique of TRISO Particle Interlayer
Charles T. Rivera (Idaho State), Tanner J. Mauseth (Idaho State), M.L. Dunzik-Gougar (Idaho State)
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