ML24271A011: Difference between revisions
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{{#Wiki_filter:Panel Session: Emerging PSA Needs with respect to Advanced Reactor Technologies | {{#Wiki_filter:Panel Session: Emerging PSA Needs with respect to Advanced Reactor Technologies Kevin Coyne US Nuclear Regulatory Commission Kevin.Coyne@nrc.gov | ||
Motivation | |||
* New and advanced designs are expected to include simplified high-reliability safety systems with reduced reliance on operator actions | * New and advanced designs are expected to include simplified high-reliability safety systems with reduced reliance on operator actions | ||
* Limited experience in performing probabilistic safety assessment (PSA) and management activities for new and advanced reactor designs | * Limited experience in performing probabilistic safety assessment (PSA) and management activities for new and advanced reactor designs | ||
| Line 23: | Line 23: | ||
* Risk metrics, mission time considerations, accident sequence identification, and end-state definitions | * Risk metrics, mission time considerations, accident sequence identification, and end-state definitions | ||
* New safety considerations, such as siting in or near populated areas or in locations exposed to more diverse hazards; transportation of fueled modules; remote or autonomous operations; and multi-module and multi-unit risk. | * New safety considerations, such as siting in or near populated areas or in locations exposed to more diverse hazards; transportation of fueled modules; remote or autonomous operations; and multi-module and multi-unit risk. | ||
* Increased reliance on passive safety features Some potential Challenges | * Increased reliance on passive safety features | ||
Some potential Challenges | |||
* How do we best use PSA technology to ensure nuclear plant safety while supporting efficient licensing and certification reviews? | * How do we best use PSA technology to ensure nuclear plant safety while supporting efficient licensing and certification reviews? | ||
* Do we need new PSA analysis and modeling techniques to address new concepts of operation (e. g., remote or autonomous operation)? | * Do we need new PSA analysis and modeling techniques to address new concepts of operation (e.g., remote or autonomous operation)? | ||
* Do new siting considerations or the use of reactors for process heat generation impact PSA modeling needs? | * Do new siting considerations or the use of reactors for process heat generation impact PSA modeling needs? | ||
* Preparing the next-generation workforce? | * Preparing the next-generation workforce? | ||
| Line 31: | Line 33: | ||
* Ensuring an adequate level of PSA technical acceptability and quality with a limited number of experts able to perform peer review activities? | * Ensuring an adequate level of PSA technical acceptability and quality with a limited number of experts able to perform peer review activities? | ||
* How can PSA techniques support the design and pre-operational phase? | * How can PSA techniques support the design and pre-operational phase? | ||
Panel | Panel | ||
* Michelle (Shelby) Bensi, Associate Professor and the Deborah J. | * Michelle (Shelby) Bensi, Associate Professor and the Deborah J. | ||
Goodings Professor in Engineering for Global Sustainability in the Department of Civil and Environmental Engineering at the University of Maryland (UMD). | Goodings Professor in Engineering for Global Sustainability in the Department of Civil and Environmental Engineering at the University of Maryland (UMD). | ||
* Seung Jun Lee, Associate Professor in the Department of Nuclear Engineering at Ulsan National Institute of Science and Technology (UNIST). | * Seung Jun Lee, Associate Professor in the Department of Nuclear Engineering at Ulsan National Institute of Science and Technology (UNIST). | ||
* Eric Thornsbury, Principal Technical Leader at the Electric Power Research Institute (EPRI). | * Eric Thornsbury, Principal Technical Leader at the Electric Power Research Institute (EPRI). | ||
Format | Format | ||
* Introduction to the session | * Introduction to the session | ||
Latest revision as of 10:29, 24 November 2024
| ML24271A011 | |
| Person / Time | |
|---|---|
| Issue date: | 09/27/2024 |
| From: | Coyne K NRC/RES/DRA |
| To: | |
| References | |
| Download: ML24271A011 (1) | |
Text
Panel Session: Emerging PSA Needs with respect to Advanced Reactor Technologies Kevin Coyne US Nuclear Regulatory Commission Kevin.Coyne@nrc.gov
Motivation
- New and advanced designs are expected to include simplified high-reliability safety systems with reduced reliance on operator actions
- Limited experience in performing probabilistic safety assessment (PSA) and management activities for new and advanced reactor designs
- New fuel designs and coolants may necessitate new analysis methods
- Risk metrics, mission time considerations, accident sequence identification, and end-state definitions
- New safety considerations, such as siting in or near populated areas or in locations exposed to more diverse hazards; transportation of fueled modules; remote or autonomous operations; and multi-module and multi-unit risk.
- Increased reliance on passive safety features
Some potential Challenges
- How do we best use PSA technology to ensure nuclear plant safety while supporting efficient licensing and certification reviews?
- Do we need new PSA analysis and modeling techniques to address new concepts of operation (e.g., remote or autonomous operation)?
- Do new siting considerations or the use of reactors for process heat generation impact PSA modeling needs?
- Preparing the next-generation workforce?
- Use of PSA methods beyond traditional event tree/fault tree methods?
- Ensuring an adequate level of PSA technical acceptability and quality with a limited number of experts able to perform peer review activities?
- How can PSA techniques support the design and pre-operational phase?
Panel
- Michelle (Shelby) Bensi, Associate Professor and the Deborah J.
Goodings Professor in Engineering for Global Sustainability in the Department of Civil and Environmental Engineering at the University of Maryland (UMD).
- Seung Jun Lee, Associate Professor in the Department of Nuclear Engineering at Ulsan National Institute of Science and Technology (UNIST).
- Eric Thornsbury, Principal Technical Leader at the Electric Power Research Institute (EPRI).
Format
- Introduction to the session
- Panelist opening remarks
- Questions, Discussion - interactive discussion and questions are strongly encouraged. Hoping for a vibrant dialogue that leverages the topics discussed throughout the conference.
- Summary discussion
- Concluding remarks from the panel