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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Digital control system installed at China’s Linglong One
Earlier this month, the first digital control system was put in place at Linglong One, a small modular reactor demonstration project being built at the Changjiang nuclear power plant in Hainan Province. This is the world’s first land-based commercial SMR and is controlled by China National Nuclear Power Co. Ltd., a subsidiary of the China National Nuclear Corporation (CNNC).
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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