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[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] 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] With the worldwide increasing energy demand, the securing of resources and energy supplies for the future has become a very important theme. There is, therefore, no doubt that the importance of nuclear development will continue to increase. So, I think we need to establish common design safety criteria as the basis of nuclear development, and also to promote the international network activities. At present, multilateral international cooperative frameworks for research and development of the next generation reactors are only INPRO and GIF. I would like to emphasize the significance of information exchange and a cooperative partnership between INPRO and GIF, and of taking advantage of the merits that both initiatives offer.
[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] Proposal for Workshop/CRP: • Is it possible to design FBR-M in 800 MWe to 1500 MWe range which eliminates the possibility of a core disruption under ATWS ? • Role of fuel type; • Role of uncertainty in feed-back parameters; • Role of decay heat estimates; • Role of flow halving time.
[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] 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] Proposals for the Second Workshop: • The advanced sodium cooled fast reactors should be competitive in comparison with alternative energy sources and meet to safety requirements for the 4th generation nuclear systems. • Mutual influence of safety and economic characteristics to each other requires to search optimal decisions on safety systems and NPP parameters on the whole, taking into account economic aspects. • The second Workshop can be dedicated to the following topics: - Optimization of inherent safety features of the advanced SFRs and their main technical and design decisions, for example, power level, NPP configuration, number of heat removal loops etc; - Search of optimal balance between passive and active safety systems in SFRs; - Approaches to mitigation of severe design basis accidents consequences in SFRs; - Analysis of potential capabilities of application of the passive safety systems to decrease cost characteristics of the advanced SFRs.
[en] Proposals of Topics for SFR Workshop: • In the 1st WS, the necessity of information exchange by experts on technical issues such as sodium reaction and passive safety was pointed out. It is expected to hold such expert meeting. • For future SFR Workshops which policy makers and experts participate in, the following issues may be suited: – Crosscutting issues on SFR safety; – Instructive Issues for the demonstration of SFR
[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.