Plenary Speakers

Catalina Anghel

Canadian Nuclear Laboratories, Canada

Presentation title:
Overview of AI/ML for reactor measurement systems and severe accident management

The recent breakthroughs in artificial intelligence (AI) and machine learning (ML) methods have led to interest in their use in nuclear science applications. The first part of this presentation will define these terms, as well as related concepts such as „big data“ and „deep learning“ (DL) to illustrate how the collection of methodologies described as „AI“ consists of both older, statistics-based methods and recent, cutting-edge neural networks. After this primer on the basics, the second part of the presentation will focus on a series of case studies in different areas of nuclear engineering. Case studies will be based on projects at Canadian Nuclear Laboratories as well as other recent research including the OECD NEA benchmarking initiatives for AI/ML for scientific computing in nuclear engineering. The concluding portion of the presentation will cover challenges and perspectives for the use of AI/ML in nuclear applications.
Catalina Anghel heads the Codes and Algorithms section at Canadian Nuclear Laboratories, which implements and develops algorithms for a variety of applications, including advanced reactor and fuel cycle modelling, atmospheric transport of radionuclides, machine learning methods for anomalous event prediction, and statistical analysis of experiments and data. Her background is in mathematics and she is a subject matter expert on data analytics and machine learning at CNL. She is currently leading the computational component of two multi-year projects.

Annalisa Manera

ETH Zurich, Laboratory of Nuclear Safety and Multiphase Flows, Zurich, Switzerland

Presentation title:
Development and application of advanced, high-resolution instrumentation for single and multiphase flows

Validation of Computational Fluid Dynamics (CFD) models require a new paradigm in experimentation. In the presentation, advanced instrumentation will be discussed specifically developed for high-resolution measurements that can be used for CFD validation. Applications to two-phase flows in bundle geometries, sodium heat pipes, high-pressure experimental facilities and buoyant flows will be presented.
Dr. Manera is Professor of Nuclear Safety and Multi-Phase Flows at ETH Zurich since July 2021 and Head of the Experimental and Computational Multiphase Flow Group at the Paul Scherrer Institute. She is the recipient of the ANS Bal-Raj Sehgal Memorial Award (2022) and the US Department of Energy CASL Director’s award (2016). She is also a Fellow of the American Nuclear Society. Between 2011 and 2021 she was Professor in the Nuclear Engineering Department of the University of Michigan. Her research group focuses on the development and application of high-resolution instrumentation for multiphase flow and on the development and application of multi-scale and multi-physics high-fidelity computational tools. Applications of her research range from large water-cooled reactors, to small modular reactors and micro-reactors. She holds a M.Sc. in Nuclear Engineering from the University of Pisa and a Ph.D. in Nuclear Engineering from the Delft University of Technology.

Bodo Mickan

Physikalisch-Technische Bundesanstalt, Braunschweig, Germany

Presentation title:
On the uncertainties of values determined in complex systems: A metrological perspective

The presentation will introduce to the situation of gas flow measurement in pipeline transport with view to the traceability down to the SI-units. On this background, essential aspects of uncertainty determination will be illustrated which are important to get a realistic estimation of the final value of interest.

Dr. Bodo Mickan Bodo Mickan studied Electrical Engineering at the University of Rostock and got his graduate engineer (Diplom Ingenieur) in 1993. Since May 1994 he has been employee of PTB. He started with research work in the field of fluid mechanics investigation installation effects on gas meters and the efficiency of flow straighteners. Based on this work he got his Ph.D. in 1998. From 1999 Bodo is working in the department for gas flow measurement and became the head of the working group for high pressure gas in 2007. In this position, he is responsible for the realization of the unit cubic meter with primary standards and the dissemination of the unit. In the international cooperation of the national metrology institutes, Bodo is the chairman of the Working Group for Fluid Flow at the BIPM. With beginning of 2023, he is also head of working group “Gas Meters” at PTB.

Joy Rempe

Rempe and Associates, LLC, USA

Presentation title:
Fukushima Daiichi: Interim Insights, Lessons Learned, and Safety Enhancements

After the March 11, 2011, accidents at the Fukushima Daiichi Nuclear Power Station (Daiichi), the U.S. as well as the international community, have worked to evaluate forensics information being obtained from the damaged facilities.   In addition to providing input to Japan regarding future decontamination and decommissioning (D&D) activities, these evaluations help provide insights about the  progression of the accidents, and where possible, reduce uncertainties in our understanding of severe accident progression.  Insights, which continue to be obtained from Japan’s D&D efforts, are used to enhance guidance for severe accident prevention, mitigation, and emergency planning.  To illustrate benefits from this effort, this paper describes selected examples emphasizing insights gained from Daiichi examinations which are being utilized within the U.S. to improve the safety and operation of existing and proposed new reactors.

Presenter:   J. Rempe, Rempe and Associates, LLC  

Contributors: M. Farmer, Argonne National Laboratory; J. Rempe, Rempe and Associates, LLC; D. Marksberry, U.S. Nuclear Regulatory Commission; and D. Peko, U.S.  Department of Energy

Dr. Joy Rempe has over 35 years’ experience in the areas of reactor safety and instrumentation performance. Prior to retiring as a Laboratory Fellow at the Idaho National Laboratory (INL), she founded an instrumentation development and deployment laboratory, which supported irradiation testing in U.S. and international facilities. During her tenure at INL, she also led numerous severe accident research efforts for U.S. and international organizations, including post-accident inspection and analysis efforts to support the Three Mile Island Unit 2 Vessel Investigation Program and efforts to investigate in-vessel retention in advanced light water reactors. As Principal of Rempe and Associates, LLC, Dr. Rempe provides consulting assistance to U.S. and international organizations. Since 2014, she has served as the technical lead for the U.S. Department of Energy (DOE) led Forensics Effort to learn from examination information obtained from the affected reactors at Fukushima Daiichi. Dr. Rempe has authored or co-authored over 400 peer-reviewed journal publications, book chapters, technical reports, peer-reviewed conference papers, and invited presentations on reactor safety, severe accident phenomena, high temperature testing, and in-pile instrumentation. She is an inventor/co-inventor of four patents (one patent winning an R&D 100 award. She currently serves as Program Review Group Chair of the OECD Fukushima Daiichi Nuclear Power Station Accident Information Collection and Evaluation (FACE) Project. Between 2010 and 2023, she was a member of the U.S. NRC Advisory Committee on Reactor Safeguards (serving as Chairman in 2022 and 2023). Between 2013 and 2019, she served as a member, and ultimately co-chair, of the DOE Nuclear Energy Advisory Committee. She holds MS and PhD degrees in Nuclear Engineering from the Massachusetts Institute of Technology and a BS degree in Nuclear Engineering from the University of Missouri – Rolla.



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Important dates

29 February 2024
Draft full-length paper due

31 March 2024
Notification of
paper acceptance

15 April 2024
Registration Deadline for Presenting Authors

15 April 2024
Early registration Deadline

17-20 June 2024