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Division Spotlight
Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Latest News
Feinstein Institutes to research novel radiation countermeasure
The Feinstein Institutes for Medical Research, home of the research institutes of New York’s Northwell Health, announced it has received a five-year, $2.9 million grant from the National Institutes of Health to investigate the potential of human ghrelin, a naturally occurring hormone, as a medical countermeasure against radiation-induced gastrointestinal syndrome (GI-ARS).
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.
