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DTSTART:20160101T000000
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BEGIN:VEVENT
DTSTART;TZID=UTC:20170313T000000
DTEND;TZID=UTC:20170315T000000
DTSTAMP:20260417T180228
CREATED:20211217T173845Z
LAST-MODIFIED:20211229T230714Z
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SUMMARY:8th International Symposium on Super-Critical Water-Cooled Reactors (ISSCWR-8)
DESCRIPTION:8th International Symposium on Super-Critical Water-Cooled Reactors (ISSCWR-8)
URL:http://15.223.132.57/event/8th-international-symposium-on-super-critical-water-cooled-reactors-isscwr-8/
CATEGORIES:Past Events
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BEGIN:VEVENT
DTSTART;TZID=UTC:20170327T000000
DTEND;TZID=UTC:20170329T000000
DTSTAMP:20260417T180228
CREATED:20211217T173830Z
LAST-MODIFIED:20211229T230714Z
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SUMMARY:CNS CANDU REACTOR TECHNOLOGY & SAFETY COURSE
DESCRIPTION:Brochure\n The course brochure is available here \nCourse Overview\nThis CNS course will present an extensive overview of the important disciplines in CANDU reactor technology and safety.  The course provides an introduction to the basic design\, technology\, and operation of nuclear reactors.  It will also present the major systems in a nuclear plant\, as well as the important CANDU reactor safety principles and systems.  How to prepare and execute safety analysis to meet licensing demands will also be discussed.  \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 to experienced professionals.  Come broaden your nuclear knowledge beyond your specific area of work and your own area of expertise.  \nThis course is eligible for Continuing Education Units in the context of the Engineering Institute of Canada Continuing Education program. \nContinental breakfast\, buffet lunch\, and coffee breaks are provided each day.  There will also be a banquet on the second evening of the course\, with an after-dinner speech highlighting a timely topic in the Canadian Nuclear industry. \nSome of the topics to be covered in the course\n\nCANDU Design\nReactor Physics\nThermalhydraulics\nReactor Operation\nBalance of Plant\nHuman Factors\nSafety Analysis\nSpent Fuel Management\nSafety Limits\nExperiments to Support Safety Criteria\nSevere Accident Management\n\n  \nObjectives of the course\n\nTo provide an introduction to CANDU technology and reactor safety\nTo present safety-analysis principles\nTo provide an overview of the major CANDU systems\nTo foster nuclear safety culture\nTo network with colleagues in the industry\n\n  \nRegistration\nThe registration fees are shown below\, and include HST (HST # 870488889RT) \n\n\nCNS Member: $950.00   [Must be a CNS member in good standing] \n\n\nNon-CNS Member: $1070.00 \n\n\nFull-time student CNS member or CNS retiree member: $400.00 \n\n\nClick here to register now. \n \nHOTEL ACCOMMODATION\nA very special room rate per night of $159 + Tax is available at the Courtyard by Marriott Downtown Toronto. To reserve your guestroom\, use this dedicated link\, but to receive this special rate you must book by February 28\, 2017; we suggest you book early to avoid disappointment. Or call 1-800-847-5075 and request the CNS Course Group Booking.
URL:http://15.223.132.57/event/cns-candu-reactor-technology-safety-course-4/
CATEGORIES:Past Events
END:VEVENT
BEGIN:VEVENT
DTSTART;TZID=UTC:20170328T000000
DTEND;TZID=UTC:20170328T000000
DTSTAMP:20260417T180228
CREATED:20211217T174248Z
LAST-MODIFIED:20211229T230714Z
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SUMMARY:Erwin Alhassan - Total Monte Carlo and Bayesian Updating in Nuclear Data Uncertainty Propagation
DESCRIPTION:Speaker:                Dr. Erwin Alhassan\, Postdoctoral Fellow\, McMaster University \nDate/Time:            March. 28st\, 1:00 pm – 2:20 pm. \nLocation:                ETB-533 (Engineering Technology Building)\, McMaster University. \nSummary \nNuclear reactors are complex multi-physics systems which require the coupling of several fields of Physics in order to describe and analyze them. In order to save time and cost\, simulations using computer codes such as MCNP6 or SERPENT are used to study safety scenarios of these systems at both steady state and transient conditions. These simulation codes use nuclear data which contain associated uncertainties as input and therefore the output of these codes are affected by the uncertainties in nuclear data used. Knowledge and the ability to quantify these uncertainties are important for setting safety margins as well as for providing confidence in the interpretation of results. Also\, in recent times\, nuclear regulatory authorities are moving away from conservative evaluations to best estimate calculations which are accompanied by uncertainty evaluations. \nIn the past because of computational resource constraint\, the propagation of uncertainties straight from nuclear model parameters to applications was difficult. However\, this is now possible due to the increase in computational power as well as improvements in nuclear reaction models. In this presentation\, the Total Monte Carlo approach and Bayesian updating for data adjustments and for nuclear data uncertainty reduction would be presented. Parameters in basic nuclear physics are sampled from uniform distributions in order to obtain non-informative priors as much as possible. These parameters are then randomly varied all together and a large set of random nuclear data libraries are produced. Next\, a probabilistic data assimilation is carried out by computing the maximum likelihood using differential experimental data. The ‘best file’ – the file with the largest likelihood function is used (in some cases) as the prior for resampling of basic nuclear parameters. Once satisfied\, the new ‘best file’ is used for creating a large set of random nuclear data libraries for the propagation step. Further\, by using the random nuclear data produced in the previous step as prior\, integral experimental data are used as an additional constraint in order to obtain a posteriori uncertainty on reactor integral quantities. \nBiography Erwin Alhassan obtained his BSc (Applied Physics with Environmental Science) and MPhil (Nuclear Engineering) from the University for Development Studies and the University of Ghana\, both in Ghana respectively. During his time in Ghana\, he has been involved in steady state\, burnup\, stability and transient analysis as well as Neutron Activation Analysis for the Ghana Research Reactor-1. He went on to obtain a Licentiate of Philosophy and a PhD (Physics with specialization in Applied Nuclear Physics) from Uppsala University in Sweden where he worked on nuclear data uncertainty quantification and data assimilation for GEN-IV reactors. He was a co-Manager and technical reviewer for the technical track 3.2 (Reactor Physics and Neutronics) for the International Youth in Nuclear Congress 2014\, Burgos\, Spain. He is currently a postdoctoral fellow at the Engineering Physics Department\, McMaster University\, Canada. He has authored/co-authored over 20 peer-reviewed journal articles and has presented papers at several international conferences and meetings.  \nCoffee and Tea will be provided at the seminar\, courtesy of the CNS. Please contact sharpejr@mcmaster.ca if you have any questions.
URL:http://15.223.132.57/event/erwin-alhassan-total-monte-carlo-and-bayesian-updating-in-nuclear-data-uncertainty-propagation/
CATEGORIES:Past Events
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