Panels Discussion
PD-A. An Overview of ASME VVUQ Standard Committees and OECD NEA Activities
Join us for an enlightening panel discussion that brings together leading participants in ASME VVUQ Standard Committees and OECD NEA to discuss their activities relevant to nuclear industry.
In this panel session, the invited speakers will:
In this panel session, the invited speakers will:
- Highlight the activities of interest to perform Verification, Validation, and Uncertainty Qualifications (VVUQ) of Thermal-Hydraulics, Computational Fluid Dynamics, and Multiphysics models relevant to Nuclear Industry.
- Present an overview of all ASME VVUQ Standard Committees.
- Present more specific activities of Committee 30 related to the computational simulation of nuclear systems thermal fluids behaviors.
- ASME and OECD activities related to Scaling Analysis will be presented next by announcing a new ASME Scaling Analysis Guide and an update of OECD Scaling Analysis Document.
- Share insights into the developments, applications, and licensing methodologies.
- Discuss the challenges and perspectives.
- Milorad Dzodzo, Westinghouse
- Joshua Kaizer, US NRC: “An overview of all ASME VVUQ Committee activities”
- Prof. Yassin Hassan, Texas A&M University: “An overview of ASME VVUQ 30 activities (validation benchmarks, scaling analysis, etc.)”
- Milorad Dzodzo, Westinghouse: “Presentation and an announcement of the ASME Standard “Scaling Methodologies for Nuclear Power System Responses”
- Prof. Francesco D’Auria, University of Pisa: “Presentation of OECD activities to update the Scaling Analysis Document “
- 1. Advance Understanding: Enhance the understanding of the progress of ASME VVUQ Standard Committees and OECD NEA activities.
- 2. Share Insights: Establish a platform for panellists to share their unique insights and experiences in the development of standards and guide documents relevant to the nuclear industry.
- 3. Discuss Challenges and Opportunities: Specify the challenges encountered in the development of standards and guide documents and explore opportunities for future developments.
- 4. Promote Dialogue: Encourage an open dialogue among global experts on the extension of standards and guide documents to broader nuclear industry applications.
- 1. How have you utilized the outcomes of the OECD NEA experimental data base for Thermal Hydraulics and CFD benchmarks in developing your analysis methodologies, and performing validations, and uncertainty quantifications?
- 2. How have you utilized the outcomes of the OECD NEA and ASME VVUQ 30 Standard Committtee Thermal Hydraulics and CFD benchmarks in developing your analysis methodologies, and performing validations, and uncertainty quantifications?
- 3. How have you utilized the developed scaling analysis methods as support of Thermal Hydraulics and CFD models development?
- 4. What could be the next priority actions for developing standards and guides relevant to the nuclear industry and licensing new types of plants.
- Industry Professionals: Gain valuable insights from the experiences of panellists participating in standards and guide documents.
- Regulators: Make informed decisions with insights relevant to developing standards and guide documents.
- Nuclear Engineers and Scientists: Stay updated on the advancements in developing standards and guide documents.
- Academics and Researchers: Enrich your research related to verification, validation, uncertainty quantification, scaling analysis and their industrial applications.
- Students: Familiarize yourself with the latest developments of standards and guide documents.
PD-B. Overview of the OECD-NEA Expert Group on Reactor Systems MUlit-Physics (EGMUP)
Over the past decades, national and multi-national efforts have been established to develop high-fidelity, multi-physics, and multi-scale M&S tools for design of and safety challenges for existing and advanced reactors. These high-fidelity, multi-physics M&S tools are being developed and utilized for a variety of applications to provide predictive capabilities that enhance safety, improve designs, and accelerate innovation. Even with the increasing fidelity and sophistication of coupled multi-physics M&S tools, the underpinning models and data always need to be validated against experiments that may require a more complex array of validation data because of the great range of the time, energy and spatial domains of the physical phenomena that are being simulated. Additionally, verification and validation processes must be established that address the mathematical coupling of the various physical phenomena that are much more complex and varied than the traditional approaches. The coupling of two or more single physics codes may accentuate the importance of some parameters due to feedback effects that are not modeled in traditional approaches. Additionally, the validation of high-fidelity, multi-physics M&S tools is further complicated by the fact that legacy data may be inadequate and the fact that few experimental facilities or methods exist to provide validation data at the resolution required.
The Expert Group on Reactor Systems Multi-Physics (EGMUP) was established in 2014 by the Nuclear Energy Agency to address specific challenges with validation of high-fidelity, multi-physics M&S tools with the intent to provide member countries with consensus guidance and recommendations and to demonstrate the application of the validation principles for both traditional and novel M&S tools. If successful, the efforts of the group will accelerate the adoption of novel modeling and simulation tools by the nuclear industry. Furthermore, it would provide a solid basis for their utilization for a wide range of applications in accordance with defense in-depth. This special session will include presentations on the overall mission of the group along with a discussion of validation exercises relevant to existing reactor technologies that aid in the development and demonstration of the validation principles.
Moderators:
The Expert Group on Reactor Systems Multi-Physics (EGMUP) was established in 2014 by the Nuclear Energy Agency to address specific challenges with validation of high-fidelity, multi-physics M&S tools with the intent to provide member countries with consensus guidance and recommendations and to demonstrate the application of the validation principles for both traditional and novel M&S tools. If successful, the efforts of the group will accelerate the adoption of novel modeling and simulation tools by the nuclear industry. Furthermore, it would provide a solid basis for their utilization for a wide range of applications in accordance with defense in-depth. This special session will include presentations on the overall mission of the group along with a discussion of validation exercises relevant to existing reactor technologies that aid in the development and demonstration of the validation principles.
Moderators:
- Timothy Valentine, ORNL
- Timothy Valentine, ORNL: “Overview of the Expert Group on Reactor Systems Multi-Physics”
- Domenico De Luca, NINE: “The Multi-Physics Pellet Cladding Mechanical Interaction Validation (MPCMIV) benchmark exercise”
- Maria Avramova, NCSU: “The TVA Watts Bar Unit 1 (TVA-WB1) multi-physics benchmark exercise”
- Kostadin Ivanov, NCSU: “The LWR-UAM multi-physics benchmark exercise”
- Evgeny Ivanov, KINS: “Overview of EGMUP Task Forces”
- 1. Advance Understanding: Deepen the comprehension of the advancements in uncertainty analysis methods and the crucial role of Input Uncertainty Quantification (IUQ) in validation of MP M&S tools.
- 2. Share Insights: Create a platform for panellists to share their unique insights and experiences.
- 3. Discuss Challenges and Opportunities: Delve into the challenges faced in the validation of MP M&S tools and explore opportunities for future advancements.
- 4. Promote Dialogue: Foster an open dialogue among global experts on the implementation of validation methodologies for MP M&S tools.
- Industry Professionals: Gain valuable insights from panellists about state-of-the-art validation of novel multi-physics M&S tools.
- Regulators: Acquire knowledge about the demonstration of validation principles for novel MP M&S tools.
- Nuclear Engineers and Scientists: Stay updated on the advancements in the validation of MP M&S tools and opportunities to participate in EGMUP activities.
- Academics and Researchers: Enrich your research validation of MP M&S tools and learn how to contribute and participate in EGMUP activities.
- Students: Learn about the latest developments in MP M&S tools and validation.
PD-C. Preservation of the most Critical Asset for BEPU, Experimental Data: Industry Efforts in Preserving and Managing Legacy Experimental Data
Join us to share best-practices and lesson learned in addressing the key problem of preserving, managing and learning from the worth of experimental data generated over last half a century. This critical asset is by far the key enabler of BEPU licensing applications. The ability to preserve, maintain and facilitate access to experimental data is the cornerstone for demonstrating the safety case of current and future nuclear power plants.
In this panel session, the invited speakers will:
Moderators:
In this panel session, the invited speakers will:
- Overview the industry and regulatory efforts in preserving legacy experimental data for the benefit of the development of credible evaluation models.
- The challenges and urgency in protecting the value of the existing experimental data, especially for test programs that precedes the digital revolution as well as the integration with new data sets being generated for the deployment of the next generation of reactors.
- Introduce industry advancements and tools that are facilitating the extraction of knowledge from the various test programs.
- Share insights into those developments, challenges and perspectives.
Moderators:
- Cesare Frepoli, FPoliSolutions
- Martina Adorni, NEA
- Stephen Bajorek, USNRC: “Preserving and Managing Legacy Experimental Data: NRC Comments and Perspective”
- Alessandro Petruzzi, NINE: “SCCRED Methodology, a NINE approach for the preservation of experimental data”
- Martina Adorni, NEA: “Preservation of key experimental data sets: NEA initiatives and future challenges”
- Cesare Frepoli, FPoli: “OGMA: a platform for preserving legacy and organizing new experimental data to support today modeling and simulation”
- 1. Advance Understanding and Promote Dialogue: Enhance awareness on the risks associated with losing the incredible value of legacy experimental data, for the benefit of current and future nuclear reactors safety case.
- 2. Share Insights: Establish a platform for panelists to share their unique insights and experiences in addressing the problem of managing the data collected from a large number of test programs over the years.
- 3. Discuss Challenges and Opportunities: Probe into the challenges encountered and explore opportunities for future advancements in the area of experimental data management and use.
- What would be the next step in addressing this important problem and what can we do to coordinate/collaborate in this issue across regulators, industry, agencies, research institutions and academia?
- Would be possible to create standards, or formulate best-practices and guidelines for maintaining these important assets across the industry? What are the challenges in your opinion? Is that even feasible?
- Do you see a tendency to rush to create new experimental data when needed rather than to first identify if relevant data already exist? How can we elevate this awareness?
- How can better utilize experimental as an industry? Do you have examples to share successes and challenges?
- What are the barriers in your opinion in sharing information for the benefit of the industry as a whole?
- Considering the multitude of advanced reactor designs and technologies evaluated today, where you see the most critical gaps in qualifying code and methods for such applications?
- Industry Professionals
- Regulators
- Nuclear Engineers and Scientists
- Academics and Researchers
- Students
PD-D. Safety Assessment and Licensing in Italy: Competences, Capabilities and Developments
Join us to be informed and participate to the discussion on how Italy is facing the issue of preparing itself to be able to address a key aspect of the nuclear technology: assessment of safety. Italy is a country willing to restart its nuclear program after phase out decision taken about forty years ago.
Notwithstanding such decision several stakeholders kept working on the nuclear sector specifically fostering the collaboration at European and Worldwide levels. Now it is the time for Italy to prepare itself to receive applications being able to judge the projects that different vendors will propose notably SMR related.
In this panel session, the invited speakers will:
Notwithstanding such decision several stakeholders kept working on the nuclear sector specifically fostering the collaboration at European and Worldwide levels. Now it is the time for Italy to prepare itself to receive applications being able to judge the projects that different vendors will propose notably SMR related.
In this panel session, the invited speakers will:
- Provide their own experiences from different perspectives including but not limited to industrial, research and governmental viewpoints.
- Present their background and capabilities as basis for establishing robust network of competences in nuclear safety and licensing.
- Discuss about advancements, R&D activities and plans to improve and reinforce the safety assessment and licensing competences and capabilities in Italy.
- Overview the industry and regulatory efforts in preserving legacy experimental data for the benefit of the development of credible evaluation models.
- The challenges and urgency in protecting the value of the existing experimental data, especially for test programs that precedes the digital revolution as well as the integration with new data sets being generated for the deployment of the next generation of reactors.
- Introduce industry advancements and tools that are facilitating the extraction of knowledge from the various test programs.
- Share insights into those developments, challenges and perspectives.
- Marco Cherubini, NINE
- Stefano Monti, AIN, ENS: “Brief notes on international nuclear safety regulation and its applicability to innovative reactors”
- Federico Rocchi, ENEA : “ENEA Experience and Capabilities for Safety Assessment”
- Andrea Bersano, SIET: “Experimental support at SIET for safety assessment of LWR and SMR”
- Marco Cherubini, NINE: “Experience and competence for safety application in licensing frameworks”
- Riccardo De Salvo, USNC: “Implications on the licensing process of the intrinsic safety characteristics of the ceramic fuel developed by the Ultra Safe Nuclear”
- Michele Frignani, Ansaldo Nucleare: “Ansaldo Nucleare and Nuclear Safety: a story of resilience”
- Massimo Morichi, TRANSMUTEX: “Technologies challenges and advances on ADS”
- 1. Provide current asset of Italian capabilities in the frame of safety assessment and licensing.
- 2. Address the Italian needs from industrial, R&D and governmental perspective.
- 3. Discuss about progress and plan for developing and strength current capabilities in view of upcoming nuclear program in Italy.
- 1. What are the challenges you have faced in dealing with safety assessment and licensing?
- 2. Which are the synergies and the opportunities that the designers see within the Italian market?
- 3. What are the expectations that designers have when submitting their proposal?
- 4. Which are the constraints and improvements that you judge relevant for the advancement of nuclear technology and licensing in Italy?
- Industry Professionals: Gather relevant information on current Italian situation and its market
- Regulators: Receive insights how a possible re-embarking country is managing the process of establishing again and reinforce nuclear competences.
- Nuclear Engineers and Scientists: Participate to the discussion about new reactor designs and concepts and related safety assessment approaches.
- Academics and Researchers: Enrich their knowledge on understand the needs for a restoration of nuclear capacity and capabilities in a country which would (re-)open to nuclear technology.
- Students: To familiarize with the needs, the challenges and the path forward to address the safety assessment and licensing capabilities in a nuclear country in view of their carrier taking the Italian panorama as practical example.
PD-E. BEPU Using Open-Source Software for Sensitivity Analysis and Uncertainty Quantification
Panel discussion on development and utilization of open-source software for sensitivity analysis and uncertainty quantification.
Moderators:
Moderators:
- Kostadin Ivanov, NCSU
- Vladimir Kriventsev, IAEA: “ONCORE Initiative and Other IAEA Activities to Support Open-Source Multi-Physics Simulation Tools For Nuclear Reactor Analysis”
- Maria Avramova, NCSU: “Open Source Based Uncertainty and Sensitivity Analysis at NCSU”
- Bernard Iooss and Joseph Mure, EDF: “Presenting the Platform OpenTURNS - An Open-Source Initiative for the Treatment of Uncertainties, Risks'N Statistics”
- Barbara Calgaro, Newcleo: “Perspectives on Open-Source Codes and Libraries for Reactor Physics, Sensitivity Analysis, and Uncertainty Quantification”
- Joshua Kaizer, U.S. Nuclear Regulatory Commission: “Embracing Uncertainty: Leveraging Open Source Software to Promote Uncertainty Quantification”
- 1. Information about current developments, national and international activities.
- 2. Share Insights about experience with applications.
- 3. Discuss challenges and opportunities.
- 4. Promote dialogue.
- Industry Professionals
- Regulators
- Nuclear Engineers and Scientists
- Academics and Researchers
- Students
PD-F. Status and perspectives of CODES and EXPERIMENTATION in nuclear thermal-hydraulics following FONESYS and SILENCE networks
Join us for a panel insightful discussion that brings together leading experts in advanced modelling and in advanced experiments and instrumentation.
In this panel session, the invited speakers will:
In this panel session, the invited speakers will:
- Present the activities of FONESYS, a network of system code and sub-channel code developers with the achievements and perspectives.
- Present SILENCE (SIgnificant Light and heavy water reactor thermalhydraulic Experiments Network for the Consistent Exploitation of the data), a network of cooperation among teams of experimentalists managing significant experimental projects in nuclear reactor thermalhydraulics.
- Discuss specific needs for new reactors related to system codes and requirements for new experimental validation.
- Discuss the challenges and perspectives for answering the BEPU needs by progressing in code modelling, code validation, improved experiments with advanced instrumentation, and in reducing uncertainties.
- Dominique Bestion, CEA
- D. Bestion: “The FONESYS activities and achievements’”
- Jean Marie Le Corre, Westinghouse: “The SILENCE activities and achievements’”
- Prof. Francesco D’Auria, University of Pisa: “CONUSAF a network of system code users“
- Prof. Yassin Hassan, Texas A&M University: “Advanced experimental methods for core 3D flow validation ”
- Jean Marie Le Corre, Westinghouse: “Needs, challenges and progress in boiling two-phase flow testing under LWR protypical conditions”
- Jean Luc Vacher, EDF: “Needs related to uncertainty analysis and contribution of the FONESYS activities in that field“
- Livia Tiborcz, GRS: “Main current difficulties to determine uncertainty of thermalhydraulic codes“
- 1. Advance Understanding: Enhance the understanding of the state of the art in modelling and experimentation and of the technical barriers
- 2. Share Insights: Panellists to share their unique insights and experiences in the development of advanced simulation tools.
- 3. Discuss Challenges and Opportunities: Specify the challenges encountered in the development of codes, benefiting from increasing computer power and multiscale simulation.
- 4. Promote Dialogue: Encourage an open dialogue among global experts on the extension of code capabilities and experimental techniques in nuclear reactor thermalhydraulics.
- 1. Express your needs and wishes on code validation and applications and code improvements.
- 2. Raise any questions related to numerical simulation, scaling analysis, experimental simulation.
- 3. How have you utilized the scaling analysis methods as support of Thermal Hydraulics code models development and have you used the codes for scaling analysis?
- 4. What could be the next priority actions for developing new code models and new experiments with new instrumentation?
- Industry Professionals: Gain valuable insights from the expertise of panellists participating in code development and experiments.
- Regulators: Make informed decisions based on updated state of the art on thermalhydraulic numerical and experimental simulation methods.
- Nuclear Engineers and Scientists: Stay updated on the advancements in code models and advanced experimental techniques.
- Academics and Researchers: Enrich your research related to code application and validation, scaling analysis and industrial applications.
- Students: Familiarize yourself with the latest developments in code models and experimental techniques.
PD-G. Why BEPU is not widespread?
Let us consider BEPU like a lake of knowledge, competence and expertise. The activities in thermal hydraulics, started in the late 70’s at the OECD/NEA/CSNI, fed the lake. Towards the end of 90’s, computational developments in different areas contributed to create what nowadays is BEPU.
Without entering the important issue-definition of what is it, validation (or V&V), scaling, uncertainty, experimentation, coupling of codes in thermal hydraulics and other disciplines (noticeably, neutron physics), tight connection with PSA and the licensing process, constitute key BEPU elements.
Definitely, BEPU collects the technology developments and allows the best (or best estimate) evaluation of reactor safety (and design-operation).
Suitable maturity for applications was achieved at the beginning of this century. Then the question arises: Why BEPU is not as widespread as it should be?
The following panellists will provide a snapshot answer (10’ each) based on their competence. All together, we invite the audience to introduce further arguments or questions.
Moderators:
Without entering the important issue-definition of what is it, validation (or V&V), scaling, uncertainty, experimentation, coupling of codes in thermal hydraulics and other disciplines (noticeably, neutron physics), tight connection with PSA and the licensing process, constitute key BEPU elements.
Definitely, BEPU collects the technology developments and allows the best (or best estimate) evaluation of reactor safety (and design-operation).
Suitable maturity for applications was achieved at the beginning of this century. Then the question arises: Why BEPU is not as widespread as it should be?
The following panellists will provide a snapshot answer (10’ each) based on their competence. All together, we invite the audience to introduce further arguments or questions.
Moderators:
- Francesco D’Auria, UNIPI
- Steve Bajorek (Regulator – research side)
- Francesco D’Auria (Research, thermal hydraulics)
- Luis Herranz (Industry/research, severe accident)
- Kostadin Ivanov (Research, neutron physics)
- Joshua Kaizer (Regulator)
- Jean-christophe Niel (Regulator)
- Chul-Hwa Song (Research, manager)
- Uwe Stoll (Industry/regulator)
- Jean-Luc Vacher (Industry)
- Enrico Zio (Research, PSA)
PD-H. Uncertainty Analysis for Multi-physics Applications
The evolution of advanced computational platforms allows the simulation of sophisticated multi-physical phenomena in a coupled fashion by incorporating neutron transport, thermal-hydraulics, fuel performance, structural mechanics, coolant chemistry, and other fields. The multi-physics simulations can be run as a single fully coupled system or can be loosely coupled with information passing back and forth from one simulator to the other at periodic intervals.
Although the modeling and simulation of nuclear reactors has made tremendous progress, there are always discrepancies between an ideal in silico designed systems and real-world manufactured ones. The presence of high dimensionality spaces (e.g., cross-sections) in connection with non-linear phenomena (e.g., thermal-hydraulics, fuel performance) poses a challenge to the current uncertainties quantification (UQ) methodologies. Thus, despite notable advancements, a crucial challenge endures: how can we precisely evaluate the uncertainties associated to these multi-physics coupled simulations?
Moderators:
Although the modeling and simulation of nuclear reactors has made tremendous progress, there are always discrepancies between an ideal in silico designed systems and real-world manufactured ones. The presence of high dimensionality spaces (e.g., cross-sections) in connection with non-linear phenomena (e.g., thermal-hydraulics, fuel performance) poses a challenge to the current uncertainties quantification (UQ) methodologies. Thus, despite notable advancements, a crucial challenge endures: how can we precisely evaluate the uncertainties associated to these multi-physics coupled simulations?
Moderators:
- Tomasz Kozlowski, UIUC
- Kaiyue Zeng, NINE
- Kaiyue Zeng, NINE: “Development of the Deterministic Sensitivity and Uncertainty Analysis Method”
- Laurent Buiron, CEA: “New Challenges in VVUQ : the Case of Fast Reactors”
- Evgeny Ivanov, IRSN: “Lessons Learned from Recent Studies of Uncertainty Quantification in Multi-Physics Modelling and Simulation”
- Gregory Delipei, NCSU: “Challenges in Uncertainty Propagation and Sensitivity Analysis for Mult-Physics Modeling and Simulation”
- Giacomo Grasso, ENEA: “Needs and Challenges in Multi-Physics Uncertainty Quantification for Lead-Cooled Fast Reactors”
- What is the state-of-the-art for forward UQ of multi-physics applications?
- What are the unique challenges and recent trends for multi-physics simulations of advanced nuclear systems?
- Can reduced order modeling speed up the UQ simulations for multi-physics applications?
- How can Scientific Machine Learning (SciML) and AI techniques be leveraged?
- How can we validate UQ methods for high-fidelity multi-physics?
- What are complete sources of uncertainties for multi-physics simulations, and can we quantify them?
- What is the difference between BEPU methodologies applied to metal-cooled reactors (e.g. SFR) and water cooled reactors (e.g. LWR)?
- What are the major uncertainty contributors to reactor simulation in the RP domain, TH domain, and FP domain? Is there a strong multi-physics correlation?
- Industry Professionals: Gain valuable insights from leading experts in UQ methodologies for multi-physics applications.
- Regulators: Inform your decisions with relevant insights into sectors where multi-physics UQ applications are crucial.
- Nuclear Engineers and Scientists: Stay abreast of advancements & applications in UQ methodologies for multi-physics systems.
- Academics and Researchers: Enhance your understanding of UQ methods and their industrial applications.
- Students: Dive into the latest developments & applications of multi-physics UQ methodologies.
PD-I. Unleashing the Power of BEPU: A Global Dialogue on Broadening Industrial Applications
Join us for an enlightening panel discussion that brings together leading experts from around the globe to discuss the expanding horizons of Best Estimate Plus Uncertainty (BEPU) methodologies in wider industrial applications.
In this panel session, the invited speakers will:
Moderators:
In this panel session, the invited speakers will:
- Highlight the benefits and limitations of BEPU methodology, and some open questions for further applications.
- Present the advancement of uncertainty analysis methods at NEA.
- Discuss on the indispensable role of Input Uncertainty Quantification (IUQ) in BEPU.
- Share insights into the development, applications and licensing of BEPU methodology.
- Discuss the challenges and perspectives.
Moderators:
- Jinzhao Zhang, TRACTEBEL
- Lucia Sargentini, CEA
- Jinzhao Zhang, TRACTEBEL: “BEPU methodology: Benefits, Limitations and Open Questions”
- Martina Adorni, NEA: “Advancing Uncertainty Analysis Methods at NEA”
- Alberto Ghione, CEA: “The Indispensable Role of IUQ in BEPU”
- Vincent Larget, EDF DT: “Industrial applications of a BEPU methodology: challenges and perspectives”
- Robert Martin, USNRC ACRS: “Insights into BEPU Applications from the USA”
- Dong Gu Kang, KINS: “Development and application of BEPU methodology in Korea”
- Alessandro Petruzzi, NINE: “The NINE Approach to BEPU Framework and Applications”
- 1. Advance Understanding: Enhance the understanding of the progress in uncertainty analysis methods and the pivotal role of Input Uncertainty Quantification (IUQ) in BEPU.
- 2. Share Insights: Establish a platform for panelists to share their unique insights and experiences in the application of BEPU methodologies in their respective countries and organizations.
- 3. Discuss Challenges and Opportunities:Probe into the challenges encountered in the application of BEPU methodologies and explore opportunities for future advancements.
- 4. Promote Dialogue:Encourage an open dialogue among global experts on the extension of BEPU methodologies to broader industrial applications.
- 1. How have you utilized the outcomes of the NEA projects on uncertainty analysis in your methodology?
- 2. What are the open issues of BEPU from a research perspective?
- 3. What is the most significant advantage and limitation of BEPU methodology from the industrial perspective?
- 4. What are the most challenging aspects of the BEPU methodology from a regulator’s perspective?
- 5. Why is BEPU methodology not widely used in place of conservative or combined analysis? How to promote it?
- 6. What are the prospects of Extended BEPU with the integration of PSA and BEPU?
- 7. What are the opportunities for applications of BEPU methodology to SMRs and AMRs design?
- 8. What can be done together to enlarge the use of BEPU methodology in licensing applications?
- 9. What could be the next priority actions to implement BEPU methodology?
- Industry Professionals: Gain valuable insights from the experiences of panelists working in industries where BEPU methodologies are applied.
- Regulators: Make informed decisions with insights relevant to areas where BEPU methodologies are applied.
- Nuclear Engineers and Scientists: Stay updated on the advancements and applications of BEPU methodologies.
- Academics and Researchers: Enrich your research related to uncertainty analysis methods, BEPU methodologies, and their industrial applications.
- Students: Familiarize yourself with the latest developments and real-world applications of BEPU methodologies.