Mr. Marek Stepniewski has more than 30 years’ experience in the commercial nuclear industry and with his thermal-hydraulic background worked mostly in areas of transient and accident analysis as well as thermo-mechanical analysis and licensing of the nuclear fuel for both BWRs and PWRs. Recent years his interest was focused mostly on Design Basis Accidents in PWRs – LOCA and RIA – both as far as modern analysis methods and newly developed or updated acceptance criteria is concerned. He was involved in several international cooperation programmes like EPRIs Fuel Reliability Program, OECD/NEAs Working Group for Fuel Safety and OECD/Studsviks SCIP III project. He served as well as a member of the Thermal-hydraulic Reference Group for Swedish Nuclear Power Board (now Swedish Radiation Safety Authority).
Dr.Jim Henshaw is a chemist with a PhD in theoretical chemistry, developing methods to solve the time dependent Schrodinger equation. Jim has extensive experience in modelling radiation chemistry phenomena and has worked on topics relating to nuclear plant chemistry and nuclear reactor water/gas chemistry for over 30 years. Initially employed at Harwell Laboratory by the United Kingdom Atomic Energy Authority 1986 he retired from the UK National Nuclear Laboratory in 2020 as its leading reactor chemist. Jim is a recognised world expert in chemistry and in particular radiation chemistry in nuclear reactor systems. Over the years he has also spent much of his time studying material and activity transport issues in a range of different reactor systems and has a good understand of how reactor chemistry impacts material corrosion and fuel behaviour. Working with organisations around the world he has investigated problems in BWRs, PWRs and gas cooled systems and helped optimise plant operations. In fact many of these reactors currently utilise software for optimising their chemistry operations that he helped develop.
Mr. Matthew Eyre has a Bachelor’s and Master’s degrees in Nuclear Engineering from the University of Virginia. He has over 40 years of experience in the operation, maintenance, fuel performance and spent fuel management of US light water reactors.
During his career, Matthew has authored and has contributed to numerous technical papers and industry articles. He has received industry awards regarding his innovations, which have improved the operations and maintenance of nuclear power plants. Matthew has patents (issued and pending) in the area of spent fuel management.
Dr. Garud has provided engineering and consulting services for over 45 years to electric utilities, research institutes, and Argonne National Laboratory. Key areas of his interest and experience include:
• Development and application of engineering models for assessing corrosion and materials degradation effects on the life and integrity of major metallic components in nuclear power systems:
− systems covering BWRs, PWRs, CANDU, and HTGR,
− environments including high temperature reactor water, steam, and helium gas, and
− effects including corrosion, oxidation, creep, fatigue, embrittlement, SCC/PWSCC, IASCC, & FAC
• Integrity assessment work related to pressure retaining components, stress–strain analysis of complex thermo-mechanical loads, 3D–plasticity effects, finite element analysis, and safety margins
• Mechanical design/analysis including integration of probabilistic, statistical, and exploratory data analysis methods in component integrity and life assessment, and use of risk/reliability methods
• Technical support in nuclear quality assurance, QA (10CFR50, Appendix B), ASME B&PV Code (Sections III and XI parts) rules and their application
• Nuclear power plant license renewal or long-term operation (LTO) and aging management programs, and related technical audits
• Engineering assessment for problem resolution and independent technical/technology reviews
Mr. Adolfo Repáraz has extensive experience in the commercial nuclear industry in the areas of fuel mechanical design and manufacturing, irradiated fuel inspection, fuel performance assessment, failed fuel diagnostics, irradiated fuel inspection tooling, manufacturing surveillances, project management, hot cell inspections, and interaction with licensing authorities.
Dr. P O Aronsson has a Ph.D. Nuclear Chemistry and has spent his main professional career at the Ringhals Nuclear Power Plant.
Mr. Szymon Duniec has a B. Sc. Degree in Radiation Physics and during the last 13 years he has been involved in the many fields.
Mr. William Server is the founding Principal of ATI Consulting and has forty years of technical experience in assessing radiation embrittlement effects, evaluation of nuclear reactor pressure vessel (RPV) surveillance programs, and structural integrity assessments of primary system components. He is an internationally acknowledged expert in the areas of small specimen fracture mechanics and management of materials aging issues, having led several IAEA Coordinated Research Programmes (CRPs) focused on extended license life of nuclear power plants. Mr. Server has consulted with organizations in Argentina, Belgium, Brazil, China, Croatia, Czech Republic, France, Japan, Korea, Mexico, Slovenia, Switzerland, United Kingdom, and USA. He has more than 150 technical paper publications.
Prof. Mr. G. Robert Odette – Distinguished Emeritus Research Professor Odette’s received his PhD from MIT in 1970, before becoming UCSB faculty member for five decades. His research focuses on developing robust methods for predicting the performance, reliability and lifetime limits of materials and structures in extremely hostile service environments; and developing new, high-performance materials, especially for nuclear fission and fusion energy applications.
Dr. David L. Chapin Fuel Material BIOGRAPHY Dr. David Chapin is an experienced professional with a diverse technical background in nuclear engineering and the nuclear fuel business acquired through more than 40 years in the field. He has a Ph.D. in Nuclear Engineering from the University of Michigan. Most of his career was spent with…