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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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
Jun 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
July 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Technical Session
Monday, May 16, 2022|10:15AM–12:00PM EDT|Pointview
Session Chair:
Andrew Godfrey
Alternate Chair:
Brenden T. Mervin
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Study of Effect of PWR Cold Leg Temperature Gradient on Reactor Core Condition
Emre Tatli (Westinghouse Electric Co.), Vefa Kucukboyaci (Westinghouse Electric Co.), Yixing Sung (Westinghouse Electric Co. )
Paper
Comparisons of Nodal Diffusion and Whole-Core Transport Methods for Multiple Cycles of a Small Light Water Reactor
Jordan D. Rader (ORNL), Andrew T. Godfrey (ORNL), Aaron M. Graham (ORNL), Clayton D. Lietwiler (Holtec International), Hunter Smith (Holtec International), Malinda Saia (Holtec International)
Determination of the Spent Fuel Decay Heat with the VERA Core Simulator
Marjan Kromar (Jožef Stefan Institute), Andrew T. Godfrey (ORNL)
VERA Neutronics High-Fidelity Benchmark for a Modern PWR Core Design
Andrew T. Godfrey (ORNL), Benjamin S. Collins (Veracity Nuclear)
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