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Division Spotlight
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.
Meeting Spotlight
2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC 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!
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Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
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Disney World should have gone nuclear
There is extra significance to the American Nuclear Society holding its annual meeting in Orlando, Florida, this past week. That’s because in 1967, the state of Florida passed a law allowing Disney World to build a nuclear power plant.
Technical Session|Sponsored by MSTD
Wednesday, November 16, 2022|10:00–11:45AM MST|Kaibab
Session Chair:
Annabelle Le Coq
Alternate Chair:
Jake R. Quincey
Session Organizer:
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Effective Thermal Conductivity of UO2-Metal Platelet Composites
10:00–10:20AM MST
JangSoo Oh (KAERI), YongSik Yang (KAERI), JaeYong Kim (KAERI)
Paper
Experimental Investigation of Degradation Mechanisms in ATF Coated Cladding Under Transient Conditions
10:20–10:40AM MST
Hwasung Yeom (Univ. Wisconsin, Madison), Tyler Dabney (Univ. Wisconsin, Madison), David Kamerman (INL), James Corson (U.S. Nuclear Regulatory Commission), Brent Heuser (Univ. Illinois, Urbana-Champaign), Kumar Sridharan (Univ. Wisconsin, Madison)
Neutronics Assessment of Advanced Fuel Claddings in the Equilibrium LWR Core Design
10:40–11:00AM MST
Kingsley Ogujiuba (NCSU), Khang Hoang Nhat Nguyen (NCSU), Yong-Joon Choi (INL), Jason Hou (NCSU)
Neutronic Analysis of Novel Accident Tolerant Control Blade in Boiling Water Reactor (BWR) Core
11:00–11:20AM MST
Arnold Pradhan (Univ. Idaho), Indrajit Charit (Univ. Idaho)
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