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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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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NRC engineers share their expertise at the University of Puerto Rico
Robert Roche-Rivera and Marcos Rolón-Acevedo are licensed professional engineers who work at the U.S. Nuclear Regulatory Commission. They are also alumni of the University of Puerto Rico–Mayagüez (UPRM) and have been sharing their knowledge and experience with students at their alma mater since last year, serving as adjunct professors in the university’s Department of Mechanical Engineering. During the 2023–2024 school year, they each taught two courses: Fundamentals of Nuclear Science and Engineering, and Nuclear Power Plant Engineering.
Technical Session|Sponsored by IRD
Monday, June 12, 2023|3:15–5:00PM EDT|Marriott 9
Session Chair:
Brenden J. Heidrich
Session Organizer:
Alternate Chair:
Lei R. Cao
The DRIFT series of experiments at Idaho National Laboratory’s TREAT transient testing facility explored pellet cracking behavior in ceramic UO2 fuel pellets at LWR-relevant conditions to create data to support modeling and simulation of fuel performance. This session will march through the irradiation testing process to highlight the steps required to turn a hypothesis into an irradiation test that can produce usable data. The DRIFT-UO2 experiment at TREAT is based on the IRP-16-10905 - Heng Ben (PITT), Mary Lou Dunzig-Gougar (ISU), “Transient Reactor (TREAT) Experiments to Validate MBM Fuel Performance Simulations” https://neup.inl.gov/SiteAssets/FY%202016%20Abstracts/IRP/IRP-16-10905_TechnicalAbstract_2016CFAAbstract10905.pdf Benjamin Spencer, et al., “Dry in-pile fracture test (DRIFT) for separate-effects validation of ceramic fuel fracture models,” Journal of Nuclear Materials, 568 (2022), https://doi.org/10.1016/j.jnucmat.2022.153816
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Structure and Process of Managing the UO2 Dry In-Pile Fracture Test Irradiation Experiment
3:15–3:35PM EDT
Leigh A. Astle (INL), Trevor J. Smuin (INL)
Paper
Neutronics Programmatic and Safety Evaluation of the DRIFT Experiment in TREAT
3:35–3:55PM EDT
Connie M. Hill (INL)
Research Objectives and Findings from the DRIFT Experiments
3:55–4:15PM EDT
Benjamin Spencer (INL), Nicolas E. Woolstenhulme (INL), Jason L. Schulthess (INL), Austin D. Fleming (INL)
Experiment Safety Analysis Process for the DRIFT Irradiation Experiment at TREAT
4:15–4:35PM EDT
Sterling S. Morrill (INL)
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