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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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 News 40 Under 40 discuss the future of nuclear
Seven members of the inaugural Nuclear News 40 Under 40 came together on March 4 to discuss the current state of nuclear energy and what the future might hold for science, industry, and the public in terms of nuclear development.
To hear more insights from this talented group of young professionals, watch the “40 Under 40 Roundtable: Perspectives from Nuclear’s Rising Stars” on the ANS website.
Hongbin Zhang (INL), Cole Blakley (Utah State Univ)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 252-261
An approach to uncertainty quantification and sensitivity analysis with coupled simulations of VERACS/ FRAPCON and VERA-CS/BISON was developed within the Multi-Physics Best Estimate Plus Uncertainty (MP-BEPU) safety analysis framework LOTUS. A single assembly model was developed for the VERA-CS simulations and FRAPCON and BISON models were developed for the hot rod in the assembly. Uncertainty quantification and sensitivity analysis were performed with 23 uncertain input parameters for the coupled VERA-CS/FRAPCON simulations and with 31 uncertain input parameters for the coupled VERA-CS/BISON simulations. The maximum fuel centerline temperature (MFCT) and gap conductance at peak power (GCPP) were selected as the figures of merit (FOM). Pearson and Spearman Correlation Coefficients, Sobol Indices and Moment Independent Delta Measures were considered in the sensitivity analysis.
