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SUMMARY:G4SR- 3 Virtual Summit
DESCRIPTION:G4SR 2024 Home Page
URL:http://15.223.132.57/event/g4sr-3-virtual-summit/
CATEGORIES:Past Events
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BEGIN:VEVENT
DTSTART;TZID=UTC:20211118T000000
DTEND;TZID=UTC:20211119T000000
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SUMMARY:CNS CANDU Thermalhydraulics Course
DESCRIPTION:2021 November 18-19 (Thursday-Friday\, Toronto Time) Course held on-line (Connection details to be communicated later after your registration) \nProgram & Brochure\n Click here for the program and course brochure \nCourse Overview\nThe first Canadian Nuclear Society (CNS) Thermalhydaulics Course was held in Toronto on December 4-5 2017. We are now offering the second CNS Thermalhydaulics Course on-line on account of the COVID-19 pandemic. \nThe objectives of this course are an overview of thermalhydraulics (TH)\, followed by broadening the area of TH as applied to CANDU reactors. The attendees will be presented with the fundamentals of TH\, the importance of TH in nuclear-energy utilization and nuclear safety\, TH phenomena\, TH discipline applied for different nuclear facilities with a focus on CANDU\, and areas of application (design\, operation\, safety evaluation\, uncertainty\, scaling\, R&D\, etc.) \nThe CNS is presenting this course to enhance the professional and technical capabilities of its members (and non-members) working in\, or interested in\, the nuclear industry.  The course is ideally suited for beginning professionals\, but also beneficial as a refresher overview course to experienced professionals.  Come broaden your nuclear knowledge beyond your specific area of work and your own area of expertise.  \nThe following topics would be covered in the course: \n\nThermalhydraulics Overview\nThermalhydraulics Fundamentals\nFuel and Fuel-channel Thermalhydraulics\nExperiments to support Thermalhydraulics\nPrimary Heat-Transport System Operations\nThermalhydraulics Computer Codes Used for Safety Demonstrations\nV&V of Thermalhydraulic Computer Codes and Simulation Uncertainty Assessment\nSafety Analysis and Trip Coverage – NEW\nContainment Thermalhydraulics – NEW\n\nBesides two NEW topics\, the existing topics will be enhanced to make the lectures easier to follow based on the feedbacks received from the last course. \nObjectives\n\nTo provide an overview of thermalhydraulics\nTo broaden the area of thermalhydraulics as applied to CANDU reactors\nTo provide an overview of the primary heat-transport system\nTo network with colleagues in the industry\n\nRegistration\nRegister         \nThe registration fees are shown below\, and include HST (HST # 870488889RT)  \nEarly-Bird Rate\n(Register by October 25\, 2021) \nCNS Member:                 $200.00   [Must be a CNS member in good standing \nNon-CNS Member:         $250.00 \nFull-time student (CNS member) or CNS retiree member:     $100.00 \n  \nRegular Rate\n(Register after October 25\, 2021) \nCNS Member:                  $250.00 [Must be a CNS member in good standing] \nNon-CNS Member:         $300.00 \nFull-time student (CNS member) or CNS retiree member:     $150.00 \nThe registration deadline is November 16\, 2021 \nRegister \nVenue\nCourse held on-line \n(Connection details to be communicated later after your registration) \n  \nBios of Lecturers/Organizers\n\n\n\n\n\nDr. Nik Popov has over 43 years of experience in the nuclear industry in Canada and internationally in various nuclear engineering disciplines including thermal-hydraulics\, safety analysis\, licensing\, computer codes development and validation\, and severe accident analysis.  In Canada\, he worked at  AECL from 1988 to 2011\, including 3 years as the Director for Safety and Licensing of new builds.  Later on he worked at SNC-Lavalin-Nuclear\, COG\, CNSC\, and OPG on various roles.  \nDr. Popov is an Adjunct Professor at the McMaster University since 2000\, where he teaches graduate courses on thermalhydraulics at McMaster and the University Network for Excellence in Nuclear Engineering (UNENE) program. Dr. Popov is also the Program Director of the UNENE Since 2016. \n\n\n\n\n  \n\n\n\n\n \n\n\nDr. David Novog is an expert in safety analysis methods and uncertainty quantification.  He holds and Industrial Research Chair in Nuclear Safety and has been a professor at McMaster since 2006.   \nFrom 1998-2006 he worked at Ontario Hydro\, OPG\, Nuclear Safety Solutions and AMEC in the areas of reactor physics\, thermal hydraulics and reactor trip assessment.  Prior to these positions he was a visiting researcher at Mitsubishi Heavy Industries in Japan on their APWR project. \nHis current research is focused on experimental and analytic issues related to fuel and fuel channel integrity and severe accident modelling.  He has large projects underway on improved maintenance instrumentation and applied radiation imaging. \n\n\n\n\n  \n\n\n\n\n \n\n\nDr. Yujun Guo is a technical specialist at the CNSC since 2008\, responsible for technical assessments of CANDU safety issues. \nDr. Guo holds a Ph.D. degree in nuclear engineering. His early career was with academia\, as an associate professor at Xi’an Jiaotong University\, China\, dedicated to R&D on experimental and analytical reactor thermalhydraulics and safety analyses. In 2001\, Dr. Guo joined AECL (now CNL) as a scientist leading a group of professionals responsible for large-scale CANDU fuel thermal-hydraulic experiments and associated data analysis and model development. \nAltogether\, Dr. Guo has had more than 35 years of experience in reactor design\, safety analysis and associated R&D activities. \n\n\n\n\n  \n\n\n\n\n \n\n\nJun Yang has been working at the Canadian Nuclear Laboratories since 2005. He is a senior scientist and the head of the Thermalhydraulics Experiments Section. \nJun is a recognized expert in experimental and analytical reactor fuel/core and system thermalhydraulics\, particularly in the areas of critical heat flux (CHF)\, post dryout (PDO) heat transfer\, pressure drop\, nucleate and film boiling\, and the header phenomena. He is the principal developer of the CHF\, PDO heat transfer\, and pressure drop prediction methods now being used by the CANDU industry. \n\n\n\n\n  \n\n\n\n\n \n\n\nJohn Froats has over 45 years of nuclear industry experience including many plant roles including as a Licenced Shift Manager and the executive role of Chief Nuclear Engineer and VP Engineering and Modifications. He led the CANDU Owners Group as President and CEO and the CSA Nuclear Standards Program as Chair. \nHe has taught approximately 2\,000 students on subjects including safety culture\, nuclear design methods\, nuclear safety design and power plant operation. \nJohn is currently an Associate Professor and Nuclear Engineer in Residence at Ontario Tech University. He remains fully active in the nuclear sector and in educational work in support of the sector. \n\n\n\n\n  \n\n\n\n\n \n\n\nDr. Qiang Cui is a senior safety specialist at Candu Energy. He has 20+ years’ experience in the CANDU nuclear industry with in-depth knowledge of deterministic safety analysis methodology\, CANDU design and operation\, especially in the heat transport system and the containment system. \nDr. Cui is a technical expert in containment and trip coverage.  He is actively involved in new CANDU designs.  He has been working on deterministic safety analyses in support of the operation and refurbishment of CANDU stations.  He has interacted with CNSC to resolve CNSC’s comments on containment and trip coverage analyses. \nDr. Cui holds a Ph.D. in mechanical engineering from University of Toronto and currently is a professional engineer in Ontario. \n\n\n\n\n  \n\n\n\n\n \n\n\nAleksandar Delja finished his graduate and postgraduate studies at the University of Belgrade (Serbia). His academic work started at the same university in the areas of energy\, thermal\, nuclear engineering. In the late 1980s he joined the nuclear industry (Siemens UB KWU) in Germany where he worked as a lead in research and development of transient thermalhydraulic computer codes. Later\, he joined IRSN\, the technical support institute of the French regulator. Since the mid-1990s\, he has been working at the CNSC (AECB) as a technical specialist in thermalhydraulics. \nAleksandar has 40 years of experience in nuclear safety\, nuclear engineering/physics and reactor thermalhydraulics. He has been a Canadian CAMP representative for more than a decade. \n\n\n\n\n  \n\n\n\n\n \n\n\nGeoff Waddington has over 25 years of experience in nuclear thermalhydraulics (TH) analysis\, mostly with AECL and CNL. He is an industry expert in system and subchannel TH\, and in the application of CFD codes. He has been involved in the development\, V&V and application of TH analysis codes ASSERT-PV and CATHENA. \nCurrently\, Geoff is the head of the Safety Analysis & Uncertainty Section at CNL\, contributing to the development of a TH analysis capability for SMR\, the assessment of next generation TH codes for CANDU applications\, and the advancement of subchannel and CFD tools for CANDU analysis.  \nGeoff has an Honours B.Math degree from the University of Waterloo (1989)\, and an M.Sc.E. degree from Queen’s University (1994). \n\n\n\n\n  \n\n\n\n\n \n\n\nVincent has 28 years of experience in the CANDU nuclear industry. He has worked on a number of CANDU-6 refurbishment projects\, Darlington safety analyses\, and Bruce-A restart safety analyses. \nVincent has in-depth understanding of the shutdown systems design and extensive experience in trip coverage analysis. He leads and provides oversight on safety analysis for various commercial and CANDU 6 development projects\, including the resolution of GAIs\, CSIs.  \nVincent has in-depth knowledge of Deterministic Safety Analysis methodology\, CANDU 6 design and operation\, and regulatory standards (a member of CSA N290.15 and CSA N290.19 technical sub-committee). He is also experienced in interacting with CNSC and regulators abroad. \n\n\n\n\n  \n\n\n\n\n \n\n\nDr. Wei Shen received his Bachelor degree (in 1988) and Ph.D. degree (in 1993) in nuclear engineering from Xi’an Jiaotong University\, China. Wei has been working on both PWR and CANDU industry and regulatory body for over 30 years as an expert on reactor physics\, and reactor safety. \nWei works as Safety and License Program Manager at COG since 2017. Prior joining COG\, Wei worked as a Technical Specialist at the CNSC for 5 years\, and worked as a reactor physicist at AECL for 14 years and was promoted as the Principal Specialist (the top technical position) in 2009. \nWei is the Chair of Nuclear Science & Engineering Division of the CNS. Wei also serves as an Adjunct Full Professor with Royal Military College of Canada and with Xi’an Jiaotong University\, China. \n\n\n\n\n  \n  \nContacts\nCourse contact (not for registration): Wei Shen\, wei.shen@candu.org  \nFor registration questions\, contact Elmir Lekovic\, cns_office@cns-snc.ca
URL:http://15.223.132.57/event/cns-candu-thermalhydraulics-course-2/
CATEGORIES:Past Events
END:VEVENT
BEGIN:VEVENT
DTSTART;TZID=UTC:20211129T000000
DTEND;TZID=UTC:20211201T000000
DTSTAMP:20260411T143820
CREATED:20211217T175936Z
LAST-MODIFIED:20220411T180427Z
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SUMMARY:Second Conference on AI\, ML and other Innovative Technologies in the Nuclear Industry (CAIMIN 2021)
DESCRIPTION:Official website: https://www.cns-ai-nuclear.com/
URL:http://15.223.132.57/event/second-conference-on-ai-ml-and-other-innovative-technologies-in-the-nuclear-industry-caimin-2021/
CATEGORIES:Past Events
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