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Benchmark Analysis of EBR-II Shutdown Heat Removal Tests

English IAEA-TECDOC-1819 978-92-0-105517-0
480 400 18.00 2017

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This publication presents the results and main achievements of an IAEA coordinated research project to verify and validate system and safety codes used in the analyses of liquid metal thermal hydraulics and neutronics phenomena in sodium cooled fast reactors. The publication will be of use to the researchers and professionals currently working on relevant fast reactors programmes. In addition, it is intended to support the training of the next generation of analysts and designers through international benchmark exercises

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Nuclear Reactors, Shutdown, Heat, Transmission, Mathematical Models, Fast Reactors, Sodium Cooled Reactors, Benchmark Analysis, EBR-II, CRP, Coordinated Research Project, Tests, System Analysis, Shutdown Heat Removal Tests, SHRT, Data, Safety Codes, Sodium Cooled Fast Reactor, SFR, Training, Lessons Learned, Methods, Models, Thermal Hydraulic Methods, Simulation Codes, Neutronics, Sensitivity Analysis, Qualification Process

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