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Division Spotlight
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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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About Studsvik Scandpower
Studsvik Scandpower (SSP) is the leading global provider of vendor-independent, state-of-the-art nuclear fuel management software and world-class engineering services. SSP offers a full suite of software product offerings, training, and engineering services, to support operating utilities, fuel vendors, safety authorities, and research organizations around the world.
Workshop
Thursday, April 8, 2021|11:45AM–1:00PM EDT
Session Chair:
Mihai A. Diaconeasa
Alternate Chair:
Arjun Earthperson (NC State Univ.)
Session Organizer:
Edward Chen (NC State Univ.)
Track Organizer:
Session Producers:
Alp Tezbasaran (NCSU)
How safe is safe enough? Probabilistic Risk Assessment (PRA), also called Quantitative Risk Assessment (QRA), has been very effective in supporting better decisions on how to manage safety by making the risks involved, the contributors, and the options for controlling the risk transparent; and, quantifying the uncertainties, the primary contributor to rare event risk. Moreover, a new generation of methodologies, often referred to as Dynamic PRA (DPRA) or simulation-based PRA, is starting to receive attention for nuclear reactor PRA. These methodologies explicitly account for the time element in the probabilistic system evolution, quantify the effects of phenomenological variability and uncertainties, and are driven by plant analysis tools (e.g., RELAP, MAAP5) to model possible dependencies among failure events that may arise from hardware/software/human interactions. They have shown great promise in reducing user-to-user analysis variability, modeling passive safety systems, aging effects, and human performance. This workshop will cover the principles of PRA, hands-on examples, as well as brief reviews of recent developments in simulation-based PRA methodologies.
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