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.
Klas Lundgren graduated 1973 in M.S Engineering Physics, Chalmers University of Technology, Gothenburg, Sweden. He joined ASEA-ATOM (later ABB Atom) in 1973 and was one of the founders of ALARA Engineering in 1995, which from 2008 was incorporated in Studsvik Nuclear. Main areas of interest have been:
• BWR water chemistry, radiation and materials – sampling and analysis, cleanup systems, condensate, feed and reactor water chemistry, gamma scanning and radiation measurements, Hydrogen Water Chemistry, radiochemistry evaluations, ALARA reviews in European and US BWRs, computer models for activity buildup in BWRs, post-accident analysis, computerized plant chemistry and activity data systems, radioactivity monitoring systems, radwaste and offgas systems. Plant-Life-Extension (PLEX)
• PWR water chemistry and radiation – Radiolysis chemistry, activity build-up, safety analysis and source terms
• Radiation shielding and radiation technology – computer code development, shielding design of BWRs and waste handling facilities, neutron transport calculation for activation and criticality analysis, radiation surveillance at power plants, reactor decommissioning analysis, safety analysis reports. shielding and neutron activation calculations of proton cyclotrons.
Klas Lundgren graduated 1973 in M.S Engineering Physics, Chalmers University of Technology, Gothenburg, Sweden. He joined ASEA-ATOM (later ABB Atom) in 1973 and was one of the founders of ALARA Engineering in 1995, which from 2008 was incorporated in Studsvik Nuclear. Main areas of interest have been:
• BWR water chemistry, radiation and materials – sampling and analysis, cleanup systems, condensate, feed and reactor water chemistry, gamma scanning and radiation measurements, Hydrogen Water Chemistry, radiochemistry evaluations, ALARA reviews in European and US BWRs, computer models for activity buildup in BWRs, post-accident analysis, computerized plant chemistry and activity data systems, radioactivity monitoring systems, radwaste and offgas systems. Plant-Life-Extension (PLEX)
• PWR water chemistry and radiation – Radiolysis chemistry, activity build-up, safety analysis and source terms
• Radiation shielding and radiation technology – computer code development, shielding design of BWRs and waste handling facilities, neutron transport calculation for activation and criticality analysis, radiation surveillance at power plants, reactor decommissioning analysis, safety analysis reports. shielding and neutron activation calculations of proton cyclotrons.
Klas Lundgren graduated 1973 in M.S Engineering Physics, Chalmers University of Technology, Gothenburg, Sweden. He joined ASEA-ATOM (later ABB Atom) in 1973 and was one of the founders of ALARA Engineering in 1995, which from 2008 was incorporated in Studsvik Nuclear. Main areas of interest have been:
• BWR water chemistry, radiation and materials – sampling and analysis, cleanup systems, condensate, feed and reactor water chemistry, gamma scanning and radiation measurements, Hydrogen Water Chemistry, radiochemistry evaluations, ALARA reviews in European and US BWRs, computer models for activity buildup in BWRs, post-accident analysis, computerized plant chemistry and activity data systems, radioactivity monitoring systems, radwaste and offgas systems. Plant-Life-Extension (PLEX)
• PWR water chemistry and radiation – Radiolysis chemistry, activity build-up, safety analysis and source terms
• Radiation shielding and radiation technology – computer code development, shielding design of BWRs and waste handling facilities, neutron transport calculation for activation and criticality analysis, radiation surveillance at power plants, reactor decommissioning analysis, safety analysis reports. shielding and neutron activation calculations of proton cyclotrons.
Klas Lundgren graduated 1973 in M.S Engineering Physics, Chalmers University of Technology, Gothenburg, Sweden. He joined ASEA-ATOM (later ABB Atom) in 1973 and was one of the founders of ALARA Engineering in 1995, which from 2008 was incorporated in Studsvik Nuclear. Main areas of interest have been:
• BWR water chemistry, radiation and materials – sampling and analysis, cleanup systems, condensate, feed and reactor water chemistry, gamma scanning and radiation measurements, Hydrogen Water Chemistry, radiochemistry evaluations, ALARA reviews in European and US BWRs, computer models for activity buildup in BWRs, post-accident analysis, computerized plant chemistry and activity data systems, radioactivity monitoring systems, radwaste and offgas systems. Plant-Life-Extension (PLEX)
• PWR water chemistry and radiation – Radiolysis chemistry, activity build-up, safety analysis and source terms
• Radiation shielding and radiation technology – computer code development, shielding design of BWRs and waste handling facilities, neutron transport calculation for activation and criticality analysis, radiation surveillance at power plants, reactor decommissioning analysis, safety analysis reports. shielding and neutron activation calculations of proton cyclotrons.
Klas Lundgren graduated 1973 in M.S Engineering Physics, Chalmers University of Technology, Gothenburg, Sweden. He joined ASEA-ATOM (later ABB Atom) in 1973 and was one of the founders of ALARA Engineering in 1995, which from 2008 was incorporated in Studsvik Nuclear. Main areas of interest have been:
• BWR water chemistry, radiation and materials – sampling and analysis, cleanup systems, condensate, feed and reactor water chemistry, gamma scanning and radiation measurements, Hydrogen Water Chemistry, radiochemistry evaluations, ALARA reviews in European and US BWRs, computer models for activity buildup in BWRs, post-accident analysis, computerized plant chemistry and activity data systems, radioactivity monitoring systems, radwaste and offgas systems. Plant-Life-Extension (PLEX)
• PWR water chemistry and radiation – Radiolysis chemistry, activity build-up, safety analysis and source terms
• Radiation shielding and radiation technology – computer code development, shielding design of BWRs and waste handling facilities, neutron transport calculation for activation and criticality analysis, radiation surveillance at power plants, reactor decommissioning analysis, safety analysis reports. shielding and neutron activation calculations of proton cyclotrons.
Klas Lundgren graduated 1973 in M.S Engineering Physics, Chalmers University of Technology, Gothenburg, Sweden. He joined ASEA-ATOM (later ABB Atom) in 1973 and was one of the founders of ALARA Engineering in 1995, which from 2008 was incorporated in Studsvik Nuclear. Main areas of interest have been:
• BWR water chemistry, radiation and materials – sampling and analysis, cleanup systems, condensate, feed and reactor water chemistry, gamma scanning and radiation measurements, Hydrogen Water Chemistry, radiochemistry evaluations, ALARA reviews in European and US BWRs, computer models for activity buildup in BWRs, post-accident analysis, computerized plant chemistry and activity data systems, radioactivity monitoring systems, radwaste and offgas systems. Plant-Life-Extension (PLEX)
• PWR water chemistry and radiation – Radiolysis chemistry, activity build-up, safety analysis and source terms
• Radiation shielding and radiation technology – computer code development, shielding design of BWRs and waste handling facilities, neutron transport calculation for activation and criticality analysis, radiation surveillance at power plants, reactor decommissioning analysis, safety analysis reports. shielding and neutron activation calculations of proton cyclotrons.
Juan de Dios Sánchez has a degree in Industrial Chemistry and has been linked to Cofrentes Nuclear Plant in Spain most of his career. Juan started his work at the nuclear industry in 1982 at Valdecaballeros project and, in 1983, he joined the Cofrentes project for the systems commissioning and startup test. He participated in the set up of the chemistry and radiochemistry laboratories and later on he was appointed as radwaste supervisor and he lead the waste cement system and condensate clean-up filters improvements. He took over Chemistry and Radiochemistry management in 1991 until mid 2006. In this period he played an important role in different chemistry improvement projects such as Depleted Zinc addition, Hydrogen Water Chemistry, Recirculation System Chemical Decontamination and On Line Noble Metal Implementation, as well as in the Plant Environmental Management System. In 2006 he was appointed to lead the Plant Life Management Program, that aims to identify the degradation mechanisms of the safety related structures, systems and components and stablish its mitigation and surveillance through the Aging Management Programs. The Plant Life Management Program has been the main support for the last Cofrentes License Renewal application presented to the CSN regulatory body. This renewal covers a period that exceeds the initial 40 years life original design of Cofrentes and the operating license was granted in 2020. Juan has particitated in different international projects, such as EPRI BWRVIP, EPRI BWR Water Chemistry Guidelines, BWR European Forum, IAEA iGALL. He has lectured on Chemistry at the Master of Applied Nuclear Ingeneering (MINA) at Universidad Autónoma de Madrid and CIEMAT, and took part as a lecturer in several fuel and materials seminars.
Arthur Motta is Professor of Nuclear Engineering and Materials Science and Engineering at Penn State University. He holds degrees in Mechanical Engineering and Nuclear Engineering from the Federal University of Rio de Janeiro, Brazil, and a Ph.D. in Nuclear Engineering from the University of California, Berkeley. Before joining the Penn State faculty in 1992, he worked as a research associate for the CEA at the Centre for Nuclear Studies in Grenoble, France, for two years and as a post-doctoral fellow for AECL at Chalk River Laboratories in Canada.
Prof. Motta works in the area of radiation damage and environmental degradation to materials with specific emphasis in Zr alloys, with projects in the areas of mechanical testing, corrosion and radiation damage. He has special interests in using advanced characterization techniques such as x-ray scattering from synchrotron radiation sources, transmission electron microscopy, and in situ irradiation to discern fundamental mechanisms of corrosion and radiation damage. He has published over 150 refereed papers and graduated more than 30 students, 7 of whom are now university professors and many others researchers at National Laboratories, government and industry.
Prof. Motta is a Fellow of the American Nuclear Society (ANS) and in 2015 he received the Mishima Award from the ANS for outstanding contributions in research and development work on nuclear fuel and materials. In 2016 he was awarded the ASTM William J. Kroll Medal for sustained impactful contributions to zirconium metallurgy including corrosion, hydriding, mechanical properties and irradiation effects. With his former advisor Don Olander, he co-wrote the two-volume textbook “Light Water Reactor Materials”, recently published by ANS, covering all aspects of materials in LWRs.
Arthur Motta is Professor of Nuclear Engineering and Materials Science and Engineering at Penn State University. He holds degrees in Mechanical Engineering and Nuclear Engineering from the Federal University of Rio de Janeiro, Brazil, and a Ph.D. in Nuclear Engineering from the University of California, Berkeley. Before joining the Penn State faculty in 1992, he worked as a research associate for the CEA at the Centre for Nuclear Studies in Grenoble, France, for two years and as a post-doctoral fellow for AECL at Chalk River Laboratories in Canada.
Prof. Motta works in the area of radiation damage and environmental degradation to materials with specific emphasis in Zr alloys, with projects in the areas of mechanical testing, corrosion and radiation damage. He has special interests in using advanced characterization techniques such as x-ray scattering from synchrotron radiation sources, transmission electron microscopy, and in situ irradiation to discern fundamental mechanisms of corrosion and radiation damage. He has published over 150 refereed papers and graduated more than 30 students, 7 of whom are now university professors and many others researchers at National Laboratories, government and industry.
Prof. Motta is a Fellow of the American Nuclear Society (ANS) and in 2015 he received the Mishima Award from the ANS for outstanding contributions in research and development work on nuclear fuel and materials. In 2016 he was awarded the ASTM William J. Kroll Medal for sustained impactful contributions to zirconium metallurgy including corrosion, hydriding, mechanical properties and irradiation effects. With his former advisor Don Olander, he co-wrote the two-volume textbook “Light Water Reactor Materials”, recently published by ANS, covering all aspects of materials in LWRs.