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[en] The INPRO Collaborative Project PRADA: INPRO PR User Requirement UR4: Innovative nuclear energy systems should incorporate multiple proliferation resistance features and measures. Goal of CP PRADA: • Development of methods for the identification and analysis of pathways for the acquisition of weaponsusable nuclear material. • Evaluation of the multiplicity and robustness of barriers against proliferation.
[en] Objectives of PR&PP Working Group: • Facilitate introduction of PR&PP features into the design process at the earliest possible stage of concept development; • Assure that PR&PP results are an aid to informing decisions by policy makers in areas involving safety, economics, sustainability, and related institutional and legal issues.
[en] The Modeling and Simulations in Core Monitoring: • Temperature distribution above the core to quantify the dilution; • Optimization of number of flow zones (more number results in complex administrative control for SA loading and lesser number calls for higher pump capacity); • Temperature / flow distributions within a SA towards deriving accurate hot spot temperatures in fuel, clad and coolant. CFD analysis of 217 pin SA with thin wire wrap demands ~ 1 million mesh size.
[en] Workshop Outcomes: • Representatives of all six SSCs gained a much fuller understanding of the ISAM, its purposes, and its application. • Overall, all six SSC representatives expressed strong support for ISAM and endorsed its value and practicality: – Clear consensus to begin using it on a trial basis; – At least two development teams are already doing so. • The only significant concern expressed by the SSCs related to resource requirements and expertise needed to apply the ISAM. • Draft ISAM document includes comments and perspectives discussed at the workshop.
[en] 2010 Main activities and outcomes: • Picture design of a Molten Salt Fast Reactor MSFR; • Development and tests of a numerical tool; • Thermal simulation of the MSFR core; • Development of salt reprocessing schemes; • The FFFER (Forced Fluoride Flow for Experimental Research) is under construction; • Corrosion studies; • Properties Measurement of reference salt systems; • MSR SSC develops links with other R&D projects; • Invited by ORNL to the Fluoride Salt-Cooled High Temperature Reactors (FHRs) workshop.
[en] Summary: • The SCWR has a strong foundation in two advanced technologies: – Advanced Gen-III water-cooled reactor technology; – Advanced supercritical fossil power technology. • Flexibility in design options to address GIF requirements • Most R&D needs are common to all designs under consideration • Major collaborative projects are signed or underway to address R&D needs.
[en] GIF Activities related to NE applications: • Topic is mainly addressed within the VHTR system: – Most projects are oriented toward co-generation, with discussions with partners from non-nuclear industry » HTTR-IS in Japan; » NHDD in Korea; » NGNP in US; » EUROPAIRS project in EU. – GIF Project Arrangement dedicated to Hydrogen Production.
[en] Conclusion: • GIF Cost Estimating Methodology is available for use by all GIF projects. • Training for users is available at varying levels of detail. • The EMWG continues to monitor Methodology applications. • Small scale activities on additional GEN IV related case studies.
[en] Proposal: • Increasing nuclear activities around the world; • Enquiry to get and be able to deliver up-to-date information on ongoing research; • Frequent request to present Generation IV systems; • The GIF could spread educational information on Generation IV systems and underlying research; • Provide a medium for lessons: – A visual aid (set of slides); – A textbook.