Short courses

As in previous years we will be running short courses on the day before the conference, Sunday 9th July.

These will be held at the conference venue, Examination Schools, which will open from 8:00am to allow for registration and an 8:30am start. The price will include all materials, tea / coffee and lunch.

There will be three courses, running concurrently, covering

Delegates on the short courses need to bring a lap-top computer

Tritium Transport in Materials

Course description

In this mini-course, you willl learn the fundamentals of hydrogen transport in materials from theory to experimental techniques and gain experience with a hands-on modelling tutorial!

The first half of the day will be dedicated to lectures by international experts covering the theory of hydrogen transport and how it is studied both numerically and experimentally. After an introduction of hydrogen (and tritium) in the field of nuclear fusion, the lecturers will cover a wide range of modelling techniques, from the atomistic scale to modelling entire reactor fuel cycles.

This course will cover the experimental techniques to measure, understand, and quantify hydrogen isotope properties in materials. The topics will cover the measurement of hydrogen diffusivity, solubility, permeability, surface reaction kinetics, and trapping sites in solid materials. The techniques and experiments relevant to hydrogen transport in fluid systems for blanket processes. As well as an overview of tritium specific diagnostics.

The second half of the mini-course will be a hands-on workshop where you will learn how to use the open-source code FESTIM (Finite Element Simulations of Tritium In Materials).Here you will learn how to run basic simulations, simulate/reproduce experiments, visualize data, and model plasma facing components.

At the end of this mini-course, you will have a very broad understanding of hydrogen transport, how to study it with experimental techniques, and have hands-on experience with simulation tools.

Start End Time Item Lecturer Content
7:30 AM 8:00 AM 00:30 Registration
8:00 AM 8:15 AM 00:15 Introduction D Andruczyk
8:15 AM 9:15 AM 01:00 Fundamentals of hydrogen transport in materials R Delaporte-Mathurin Why should we care about H in the context of nuclear fusion? And what are the key processes at stake?
9:15 AM 9:30 AM 00:15 Coffee break
9:30 AM 10:30 AM 01:00 Modelling hydrogen in materials: atomistic scale D Nguyen A review of modelling techniques from the atomistic scale up to fuel cycle
10:30 AM 11:00 AM 00:30 Modelling hydrogen in materials: component to reactor scale R Delaporte-Mathurin
11:00 AM 12:00 PM 01:00 Experimental techniques T Fuerst (INL) An overview of experimental methods to measure and characterize tritium transport in fusion reactor materials.
12:00 PM 1:00 PM 01:00 Lunch
1:00 PM 3:00 PM 02:00 FESTIM workshop 1 R Delaporte-Mathurin , J Dark Tasks 1 to 4
3:00 PM 3:15 PM 00:15 Coffee break
3:15 PM 4:45 PM 01:30 FESTIM workshop 2 R Delaporte-Mathurin , J Dark Tasks 5 to 8
4:45 PM 5:15 PM 00:30 Discussion and closing

lecturers

  • Tommy Fuerst (INL)
  • Duc Nguyen (UKAEA)
  • J Dark (CEA)
  • R Delaporte-Mathurin (MIT)

Biographies


Tommy Fuerst

Research Areas
Tritium Transport Measurements; Fusion Technology; Blankets and Fuel Cycle; Surface Characterization;

Bio
Dr. Thomas (Tommy) Fuerst joined the Fusion Safety Program at Idaho National Laboratory in 2019 as a research scientist. His research focus is hydrogen isotope interaction with fusion and fission materials and technology for tritium management in advanced reactors. His expertise is in measurement of hydrogen transport properties, membranes and membrane reactors for hydrogen separation, thin film deposition, and material characterization using techniques such as scanning auger microprobe, x-ray photoelectron spectroscopy, electron microscopy, and x-ray diffraction. Dr. Fuerst is a member of the executive committee for the American Nuclear Society Fusion Energy Division.

Education
Ph.D., Chemical Engineering – Colorado School of Mines
B.S., Chemical Engineering – University of Colorado Boulder

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Duc Nguyen-Manh

Research Area
Multiscale Materials Modelling of Radiation Damage, Models and Data for Plasma Facing Materials, Tritium Inventory Modelling from First Principles

Bio
Dr. Duc Nguyen-Manh joined Theory and Modelling Department at United Kingdom Atomic Energy Authority (UKAEA) from University of Oxford in 2003 when he was the OCAMAC Fellow at the Department of Materials. From 2017, he becomes senior research scientist at Materials Division (UKAEA).  His main research interest is focusing on fundamental understanding of microstructure evolution of materials under neutron irradiation in fusion reactor environment from integrated modelling and experimental approach. He is currently one of the work package leaders of the UKAEA Tritium Inventory Modelling program working to develop a first-principles model for tritium retention/release/permeation as input to MOOSE finite-element code. H-index:43, according to SCOPUS database. 

Education
Habilitation Diploma: Physics and Chemistry of Materials, CNRS, Greboble
Ph.D: Condensed Matter Theory, CNRS, Grenoble

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ORCID https://orcid.org/0000-0001-6061-9946


James Dark

Research Areas
Tritium Transport; Fusion Technology; Breeding blankets

Bio
James Dark, a PhD at the french Institute for Magnetic Fusion Research (CEA). His primary research focus is hydrogen transport modelling in breeding blanket. A developer of the FESTIM code. His PhD project investigates influencing factors on tritium transport in the WCLL breeder blanket for DEMO, and subsequent effects on tritium retention and tritium permeation into cooling channels.

Education
Ph.D., Material Science – University Sorbonne Paris Nord
MPhil Nucear Energy – University of Cambridge
BEng Mechanical Engineering – Coventry University

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Remi Delaporte-Mathurin

Research Areas
Fusion energy; Tritium breeding; Hydrogen transport

Bio
Dr. Delaporte-Mathurin started his career in fusion at the Culham Science Centre for Fusion Energy (UKAEA), did his Ph.D. at the french Institute for Magnetic Fusion Research (CEA) and recently joined the Plasma Science and Fusion Center at Massachusetts Institute of Technology (MIT) as a postdoc associate. His primary research focus is hydrogen transport modelling fusion in relevant materials. He is the lead developer of the FESTIM code. His Ph.D. project investigated tritium retention in the ITER divertor but his current focus is now on tritium breeding technologies through the project LIBRA. Aside from his core research, Dr. Delaporte-Mathurin has a keen interest in data visualisation and popularisation of science.

Education
Ph.D., Material Science – University Sorbonne Paris Nord
Master of Engineering – Ecole Polytechnique Nantes University

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Plasma Material Interactions for Fusion Plasmas: Fundamentals and Applications

Course description

As part of SOFE 2023, a special one–day mini course on Plasma Material Interactions for Fusion Plasmas: Fundamentals and Applications will be offered on Sunday July 09, 2023. The mini course will be held at the Oxford Examinations School, Oxford, United Kingdom. International experts from academia and national labs will provide a set of comprehensive lectures on plasma material interactions, plasma edge physics and their applications in fusion. 

The aim of the mini course is to provide a comprehensive introduction of plasma-material interactions with an emphasis on fusion plasmas. This mini course will address rising interest in the area of plasma material interaction and will in part introduce the breadth and depth of the subject including: plasma surface interactions in fusion edge plasmas, plasma diagnostics for PMI and modeling of the plasma edge and materials, where the plasma/material interface plays a crucial role in materials performance and behavior. A unique aspect of this mini course is to bring instructors who not only have an expertise in plasma-material interactions, but also extensive experience both in PMI experiments and atomistic/multi-scale computational PMI modeling. The course will uniquely describe the challenges of PMI experiments and computational modeling and the areas in which these two thrusts can complement each other. The course instructors include leading researchers in the areas of experimental and computational plasma-material interactions. 

A unique aspect of this mini course is to bring instructors who not only have an expertise in plasma-material interactions, but also extensive experience both in PMI experiments and atomistic/multi-scale computational PMI modeling. The course will uniquely describe the challenges of PMI experiments and computational modeling and the areas in which these two thrusts can complement each other. Topics include: PMI fundamentals, the plasma sheath, plasma facing components, PMI diagnostics, computational PMI, PMI of the divertor, PMI of the SOL and pedestal. The course instructors include leading researchers in the areas of experimental and computational plasma-material interactions.

Start End Time
7:30 AM 8:15 AM 00:30 Registration
8:15 AM 8:30 AM 00:15 Introduction
D Andruczyk
8:30 AM 9:15 AM 00:45 Fundamentals of PMI 1: An Overview
9:15 AM 10:00 AM 00:45 Fundamentals of PMI 2: Plasma Sheath and its interaction with Surfaces
10:00 AM 10:30 AM 00:30 Break
10:30 AM 11:30 AM 01:00 Plasma Facing Components: Liquid and Solid Solutions
Andrei Khodak
11:30 AM 12:00 PM 00:30 Discussion
12:00 PM 1:00   PM 01:00 Lunch
1:00 PM 2:00 PM 01:00 Diagnostics for PMI
Daniel Andruczyk
2:00 PM 3:00 PM 01:00 Computational PMI: Plasma Edge and Material Models
Davide Curreli
3:00 PM 3:15 PM 00:15 BREAK / Discussion
3:15 PM 4:15 PM 01:00 PMI and Scrape-Off Layer Plasma Transport
David Donovan
4:15 PM 5:15 PM 01:00 PMI in Fusion Devices
Rajesh Maingi
5:15 PM 5:30 PM 00:15 Discussion, Adjourn

lecturers

  • Rajesh Maingi (PPPL)
  • David Donovan (UTK) 
  • Andrei Khodak (PPPL)
  • Davide Curreli (UIUC)
  • Daniel Andruczyk (UIUC) 

Biographies


Rajesh Maingi

Research Areas
Tokamak confinement and boundary physics; plasma-material interactions; liquid metal plasma-facing components

Bio
Rajesh Maingi is Head of the Tokamak Experimental Sciences Department at Princeton Plasma Physics Laboratory (PPPL), and the lead investigator on a domestic liquid metal plasma-facing component development program. He has published research on the boundary plasma in many fusion devices, including Alcator C-Mod (Boston), ASDEX-Upgrade (Germany), DIII-D (San Diego), EAST (China), KSTAR (S. Korea), MAST (England), NSTX (Princeton), and TdeV (Canada), in 35 first author journal articles and more than 900 total publications. He was elected a Fellow of the American Nuclear Society in 2019, a Distinguished Research Fellow at PPPL in 2014, and a Fellow of the American Physical Society in 2009. In 2018 he received the Princeton University/PPPL Kaul Foundation Prize for Excellence in Plasma Physics Research and Technology Development. He received his Ph. D. in Nuclear Engineering from North Carolina State University in 1992. Following postdoctoral fellowships at the DIII-D device, he served on the research staff at Oak Ridge National Laboratory from 1997-2012, and joined PPPL as a Principal Research Physicist in 2012.

Education
Ph.D., Nuclear Engineering – North Carolina State University
B.S., Nuclear Engineering – North Carolina State University

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Professor David Donovan

Bio
David Donovan is an associate professor and a Zinkle Faculty Fellow in the Nuclear Engineering Department at the University of Tennessee-Knoxville (UTK). He received his PhD in Nuclear Engineering from the University of Wisconsin-Madison in 2011 and his BS in Nuclear Engineering at the University of Illinois at Urbana-Champaign.  His PhD work was in the area of Inertial Electrostatic Confinement (IEC) Fusion for the purpose of creating and utilizing small-scale neutron generating devices to detect explosives and other illicit materials.  He was a post-doctoral research associate at Sandia National Laboratories-Livermore where he worked in the area of plasma-surface interactions in magnetically confined fusion devices.  He collaborated extensively with the DIII-D tokamak operated by General Atomics in San Diego, CA as well as with the Tritium Plasma Experiment located at Idaho National Laboratory. Since joining UTK in 2014, he has developed a research program in fusion energy science, plasma physics, plasma-material interactions, and near term applications of nuclear fusion devices. He has introduced new plasma/fusion undergraduate and graduate courses including Introduction to Plasma Physics, Introduction to Fusion Technology, Plasma Diagnostics, and Boundary Plasma Physics. His group has constructed a compact electron cyclotron resonance (ECR) plasma exposure stage at UTK for low flux ion damage studies, which has been combined with material characterization tools (SEM, FIB, EBSD, GIXRD) to perform studies of He ion damage to tungsten. His research group has performed plasma and heat flux diagnostic implementation on the Proto-MPEX linear plasma device at Oak Ridge National Laboratory (ORNL) and performed surface chemistry studies at Princeton Plasma Physics Laboratory (PPPL) on the LTX-Beta device. Prof. Donovan leads a collaborative research effort with the Boundary Plasma Science program at the DIII-D fusion experiment at General Atomics in the area of diagnostic development, boundary plasma experiments, and impurity transport studies. Prof. Donovan is also part of an international collaboration with the WEST fusion experiment in Cadarache, France, which is studying the use of tungsten plasma-facing components in a long-pulse magnetically confined fusion device.


Andrei KHodak

Research Areas
Liquid metal plasma-facing components, tritium breeding blankets, computational fluid dynamics, magnetohydrodynamics; plasma-material interactions, 

Bio
Andrei Khodak is Principal Engineering Analyst at Princeton Plasma Physics Laboratory (PPPL) where he performs multi-physics modeling including plasma simulation, magneto-hydrodynamics, computational fluid dynamics, turbulence modelling, heat, and mass transfer. He worked on analysis and engineering of many existing and future fusion devices, including ITER, DIII-D (San Diego), CFETR (China), NSTX (Princeton). He received the M.Sc. degree in engineering physics and the Ph.D. degree in physics and mathematics from the St. Petersburg State Polytechnical University, Russia, in 1988 and 1991, respectively. Since then, he held various research and engineering positions in industry and academia, all related to fluid mechanics and heat transfer before joining PPPL in 2010.

Education
Ph.D., Physics and Mathematics – St. Petersburg State Polytechnical University
B.S., Engineering Physics – St. Petersburg State Polytechnical University

Social

Linkedin www.linkedin.com/in/andreikhodak

ORCID  0000-0002-8273-6614


Davide Curreli 

Research Areas
Computational Modeling of Plasma-Material Interactions, Plasma Boundary, Plasma Transport, Plasma Chemistry  

Bio
Davide Curreli is Associate Professor in the Department of Nuclear, Plasma, and Radiological Engineering at the University of Illinois Urbana-Champaign, and at the National Center for Supercomputing Applications. Dr Curreli leads the Laboratory of Computational Plasma Physics at Illinois. His research activities focus on computational modeling of plasma material interactions and plasma chemistry of low-temperature plasmas for fusion and nuclear applications. Among his current research activities, Dr Curreli is coordinator of the Nuclear Fireball Plasma Chemistry activities within the University Research Alliance funded by DoD DTRA. His group actively works on multiple projects in Fusion Energy Sciences. Dr Curreli is Donald Biggar Willett Faculty Scholar at the University of Illinois. He received a BS (2004), MS (2007), and PhD (2011) from the University of Padova, Italy. He joined the University of Illinois in 2012. 

Social

Webpage: https://npre.illinois.edu/people/profile/dcurreli 

ORCID  0000-0001-6406-6699


Daniel Andruczyk

Research Areas
Plasma Material Interactions, Plasma Facing Component Materials, Liquid Lithium Plasma Facing Technology, Plasma Edge, Diagnostics

Bio
Prof. Andruczyk is heading up the HIDRA device at the University of Illinois. Previously he was a Research Engineer at the Princeton Plasma Physics Labs from 2012 – 2014. He currently is an Research Associate Professor at the Center for Plasma-Material Interactions, a multidisciplinary center at the University of Illinois. Prof. Andruczyk conducts research into plasma edge studies and PFC materials as well as research related to manufacturing in the semiconductor industry. Prof. Andruczyk has previously worked as a post-doc at the Max Planck Institute for Plasma Physics, Greifswald where the W-7X Stellarator is located. Professor Andruczyk has extensive experience running experiments on H-1, WEGA, HIDRA (Formerly WEGA), NSTX and EAST. In conjunction with PPPL, ORNL and Illinois, Prof Andrucyk is one of the lead PI’s in the Liquid Metal PFC development program in the US.

Education
Ph.D., Plasma Physics – University of Sydney
M.S., Plasma Physics – University of Sydney
B.S (Hons)., Laser Physics – University of Queensland
B.S., Physics – University of Queensland

Social

LinkedIn

ORCID  0000-0001-6613-3509

Fundamentals of Fusion Neutronics

Course description

The aim of this course is to provide a comprehensive introduction to the impacts of fusion neutrons and the various approaches to modeling and simulating those impacts for scientists and engineers from a broad set of related disciplines. Participants of this course will be better prepared to consider the role of neutronics in their own design and analysis work across those disciplines. Some participants may be inspired to begin a deeper study of fusion neutronics, but this course will not prepare participants to perform neutronics simulations.

The instructors have extensive experience in the development of fusion neutronics capability and using that capability across systems to support nuclear design and analysis of fusion energy systems.

Start End Time
7:30am 8:30am 01:00 Registration
8:30am 8:45am 0:15 Introduction
Ethan Peterson/Jon Shimwell
8:45am 10:15am 1:30 Neutron transport
Ethan Peterson
10:15am 10:30am 0:15 Break
10:30am 12:00pm 1:30 Prompt responses to neutron radiation
Jon Shimwell
12:00am 1:00pm 1:00 Lunch
1:00pm 2:30pm 1:30 Activation
Ethan Peterson
2:30pm 2:45pm 0:15 Break
2:45pm 4:15pm 1:30 Delayed responses to neutron radiation
Jon Shimwell
4:15pm 4:45pm 0:30 Discussion
3:00 PM 3:15 PM 00:15 BREAK / Discussion
3:15 PM 4:15 PM 01:00 PMI and Scrape-Off Layer Plasma Transport
David Donovan
4:15 PM 5:15 PM 01:00 PMI in Fusion Devices
Rajesh Maingi
5:15 PM 5:30 PM 00:15 Discussion, Adjourn

lecturers

  • Paul Wilson (UW-Madison)
  • Jonathan Shimwell (First Light Fusion)
  • Ethan Peterson (MIT)

Biographies


Paul P.H. Wilson

Research Areas
Computational modeling of radiation transport; fusion neutronics; fusion nuclear design & analysis

Bio
Paul Wilson is the Grainger Professor of Nuclear Engineering and Chair of the Department of Nuclear Engineering and Engineering Physics and the University of Wisconsin-Madison.  In nearly 30 years of experience in the development of methods for modeling and simulation of fusion nuclear responses, he has led the development of tools such as DAGMC that allow the rapid modeling of complex CAD-based geometries and ALARA for determining the activation and activation responses in fusion energy systems.  He has applied these tools to ITER, IFMIF and a variety of fusion power plant design studies including the complex geometries of stellarators.

Education

PhD, Nuclear Engineering and Engineering Physics – University of Wisconsin-Madison
Dr-Ing, Mechanical Engineering – Technical University of Karlsruhe (now KIT) 
BASc, Engineering Science – University of Toronto

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Jon Shimwell

Research Areas
Fusion reactor design, Parametric modeling, neutronics workflows

Bio
Jonathan Shimwell holds a Lead Scientist position at First Light Fusion. Primarily a neutronics expert with focus on developing automated open source workflows that integrate into wider reactor design studies. Experience in fusion research at both government and start-up level including EU-DEMO, STEP, UKAEA, CFS, KIT and CEA. Previous career as a physics teacher and continues to teach neutronics at UK universities and the NEA databank. A full stack analysis working on: nuclear data processing, particle transport code development, parametric geometry creation, conversion of models, automated testing with CI/CD, user interface creation, containerised software environment creation, cloud computing / web deployment and dissemination. A contributor and creator in the open source neutronics community. Creating software packages such as Paramakneutronics-workshop and a variety of web apps on xsplot.com. A contributor to popular open source neutronics codes including OpenMC and DAGMC

Education

PhD in Physics specializing in Fusion Neutronics – University of Sheffield

PGDip Postgraduate Diploma in Professional Skills – University of Sheffield

MSc Physicals and Technology of Nuclear Reactors – University of Birmingham

PGCE Postgraduate Certificate in Education (Physics) – University of Keele

MSci Computer Science with Astrophysics – University of Keele

Social


Ethan Peterson

Research Areas
Fusion reactor design, fusion neutronics, computational plasma physics

Bio
Ethan is a Research Scientist and the Neutronics Group lead at the MIT Plasma Science and Fusion Center. Currently, he is focused on integrated modeling and experiments for fusion technology R&D with the open-source Monte-Carlo code, OpenMC. He has contributed significantly to the neutronics analysis and device design of the SPARC tokamak under construction by Commonwealth Fusion Systems in Devens, MA. In the past, he has worked on experimental and computational plasma physics for understanding both plasma-material interactions as well as the origins of the young solar wind.

Education

PhD, Physics, University of Wisconsin – Madison 

MS, Nuclear Engineering and Engineering Physics, University of Wisconsin – Madison 

MS, Physics, University of Wisconsin – Madison 

BS, Nuclear Engineering and Physics, MIT

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