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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
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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Oct 2024
Jul 2024
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Nuclear Science and Engineering
November 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Keeping up with Kewaunee
In October 2012, Dominion Energy announced it was closing the Kewaunee nuclear power plant, a two-loop 574-MWe pressurized water reactor located about 27 miles southeast of Green Bay, Wis., on the western shore of Lake Michigan. At the time, Dominion said the plant was running well, but that low wholesale electricity prices in the region made it uneconomical to continue operation of the single-unit merchant power plant.
June 15–18, 2025 | Chicago, IL | Chicago Marriott Downtown Magnificent Mile
Honorary Chair
Karl N. Fleming (KNF Consulting Services)
General Chair
Rick Grantom (CRG)
Program Chair
Dave Grabaskas (Argonne National Laboratory)
PSA ABSTRACTS SUBMISSION: OCTOBER 14, 2024
AUTHOR NOTIFICATION: MARCH 3, 2025
FULL PAPERS SUBMISSION: FEBRUARY 3, 2025
FINAL PAPERS DUE: MARCH 17, 2025
Since 1978, the ANS biennial topical conference on Probabilistic Safety Assessment (PSA) has been a worldwide forum for communication of major probabilistic risk and safety topics, including issues, methods, applications, insights, policy, research, and risk-informed regulation experience. The 19th PSA meeting, sponsored by the ANS Nuclear Installations Safety Division, will highlight the role of probabilistic methods in understanding uncertainties; improving the safety and security of the current nuclear facilities; and supporting the design, licensing, operation, and other riskinformed applications of the next generation of reactors.
PSA 2025 is structured to foster interaction and collaboration across topic areas, leading to increased understanding and application of PSA in all phases of nuclear power plant design and operation. The use of PSA has continually increased over the last decade with reliance on PSAs and associated risk-informed applications at its highest point in nuclear industry history.
We welcome and encourage students to submit papers to this conference. Please ensure that abstracts/ papers for which the Primary Author is a student are identified as such in the yes/no student status question in the Authors section of the EPSR. Judges will use this information to identify the conference’s best student papers, which will receive a cash prize.
Outstanding papers will be selected for publishing in a special issue of Nuclear Technology. Nuclear Technology is the leading international publication reporting new information on the practical application of nuclear science for peaceful uses.
We are first soliciting abstracts with a maximum length of one page to be reviewed. Full papers with a length of 7-10 pages will be required if the abstract is accepted. Abstracts should include an identifying title, authors, affiliations, and two to three paragraphs (total fewer than 500 words) describing the key concepts of the paper. Use the provided template. A wide range of topic areas are highlighted on p. 2; however, papers regarding safety and risk beyond the listed topics are also encouraged.
For those interested in organizing panel sessions, please prepare and submit an abstract with a description of the session and potential speakers. For those interested in organizing workshops or similar, please contact the conference organizers.
1. PSA METHODS, ANALYSES, AND APPLICATIONS 1.1. Level 1, 2, 3 PSA Applications 1.2. Full Scope Internal/External Event PSA Models, Applications, Feedback, and Lessons Learned1.3. Low Power and Shutdown PSA1.4. Multi-Unit Risk1.5. Risk Informed Cyber Security1.6. Extended Accident Risk, FLEX Effectiveness1.7. Aggregation and Integration of PSA Hazard Group Models1.8. Risk-Informed Physical Security1.9. Proliferation Risks1.10. Transportation Risks1.11. Risk-Informed Onsite Waste Storage1.12. Repository PSA1.13. Micro-reactor PSAs1.14. SMR PSAs 1.15. Non-LWR PSAs1.16. Risk Analysis of Hybrid and Integrated Energy Systems1.17. Risk Analysis for Test/Research Reactor and Non-Reactor Nuclear Facilities1.18. Grid Resiliency and Reliability1.19. Fuel Cycle Accident Risk1.20. Non-Core Radioactivity Source Risk1.21. Risk Management1.22. Economic Risks1.23. Health Risks1.24. Risk Tradeoffs1.25. Characterization of Risks1.26. PSA Verification and Validation1.27. PSA Tool Development1.28. Dynamic PSA 1.29. Simplified Risk Assessments1.30. Risk-Informed Margins Methods1.31. Success Path Methods1.32. PSA Software and Tools1.33. Safety Culture, Socio-Technical and Organizational Safety Risk Analysis
2. SAFETY ASSESSMENT METHODS, ANALYSES, AND APPLICATIONS 2.1. Plant Response to Events2.2. Safety Assessment2.3. Human Reliability Analysis2.4. Dependent Failure Analysis2.5. Margin Assessment2.6. Uncertainty Quantification/Treatment of Uncertainties Sensitivity Analysis2.7. Digital Twins and Risk Analysis2.8. Artificial Intelligence and Machine Learning for Risk Analysis2.9. Component Reliability2.10. Source Term Analysis2.11. Digital l&C and Software Reliability2.12. Passive System Reliability2.13. Integrated Safety Assessment2.14. Long Term Operations and Risk Informed Aging Management2.15. Availability Modeling and Maintenance Optimization2.16. Operational Experience and Data Analysis
3. RISK-INFORMED REGULATION, STANDARDS, AND DECISION-MAKING 3.1. Risk-Informed, Performance-Based Regulation 3.2. Risk-Informed Licensing Strategies3.3. 10 CFR 50.69 Alternative Treatment Approaches and Applications3.4. 10 CFR Part 53: Risk-Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors3.5. Licensing Modernization Project Feedback and Lessons Learned3.6. Risk-Informed Management Programs (Technical Specifications, Maintenance, Internal Fire, NFPA 805)3.7. Risk Informed Codes and Standards3.8. Risk-Informed, Technology-Inclusive Design Standards3.9. Risk-Informed Design and Construction3.10. Risk-Informed Surveillance Program3.11. Risk-Informed Technical Specifications3.12. Risk-Informed Emergency Planning3.13. Cost Savings through Risk-Informed Methods 3.14. Incorporation of Risk Insights in Decision-Making3.15. Establishing Risk Acceptance Criteria3.16. Consideration of Risk-Informed Regulations3.17. Knowledge Transfer and Management
https://epsr.ans.org/meeting/?m=422
Janet Davis 708-579-8253 jdavis@ans.org