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Showing results 1 to 20 of 35

Issue DateTitleAuthor(s)TypeView
2020-04Adjoint-based sensitivity analysis of circulating liquid fuel system for the multiphysics model of molten salt reactorJeong, Yeong Shin; Cervi, Eric; Cammi, Antonio; Ninokata, Hisashi; Bang, In CheolARTICLE123
2015-05-18CFD analysis of a concept of hybrid control rod with heat pipeJeong, Yeong Shin; Kim, Kyung Mo; Kim, In Guk; Bang, In CheolCONFERENCE21
2018-08-10CFD simulations of pool boiling with various heater wall conditionsJeong, Yeong Shin; Bang, In CheolCONFERENCE25
2015-09Comparison of thermal performances of water-filled, SiC nanofluid-filled and SiC nanoparticles-coated heat pipesKim, Kyung Mo; Jeong, Yeong Shin; Kim, In Guk; Bang, In CheolARTICLE548
2015-10-30Cooling Performance Evaluation of the Hybrid Heat Pipe for Spent Nuclear Fuel Dry Storage CaskJeong, Yeong Shin; Bang, In CheolCONFERENCE12
2015-06-25Cooling Performance of the Hybrid Heat Pipe of the Spent Nuclear Fuel Dry Storage usign CFDJeong, Yeong Shin; Bang, In CheolCONFERENCE10
2015-10-16Design and Simulation of Heat Pipe-based Passive Cooling Device for spent Fuel Dry Storage CaskJeong, Yeong Shin; Bang, In CheolCONFERENCE7
2015-10-16Development of Passive In-Core Cooling System (PINCs) Based on Hybrid Heat PipeKim, Kyung Mo; Jeong, Yeong Shin; Kim, In Guk; Bang, In CheolCONFERENCE12
2016-12Development of passive in-core cooling system for nuclear safety using hybrid heat pipeKim, Kyung Mo; Jeong, Yeong Shin; Kim, In Guk; Bang, In CheolARTICLE505
2020-06Dynamic mode decomposition for the stability analysis of the Molten Salt Fast Reactor coreDi Ronco, Andrea; Introini, Carolina; Cervi, Eric; Lorenzi, Stefano; Jeong, Yeong Shin; Seo, Seok Bin; Bang, In Cheol; Giacobbo, Francesca; Cammi, AntonioARTICLE44
2020-01Enhanced heat transfer and reduced pressure loss with U-pattern of helical wire spacer arrangement for liquid metal cooled-fast reactor fuel assemblyJeong, Yeong Shin; Kim, Ji Yong; Bang, In CheolARTICLE188
2015-05-07Experimental investigation on heat transfer performance of annular flow path heat pipeKim, In Guk; Kim, Kyung Mo; Jeong, Yeong Shin; Bang, In CheolCONFERENCE15
2015-09-02Experimental Investigation on Heat Transfer Performance of Annular Heat Pipe for Passive IN-Core Cooling SystemKim, In Guk; Kim, Kyung Mo; Jeong, Yeong Shin; Bang, In CheolCONFERENCE22
2016-05-12Experimental Study of Hydraulic Control Rod Drive Mechanism for Passive IN-core Cooling System of Nuclear Power PlantKim, In Guk; Kim, Kyung Mo; Jeong, Yeong Shin; Bang, In CheolCONFERENCE12
2015-09-01Feasibility Study of Hybrid Heat Pipe with Control Rod as Passive In-Core Cooling System for Advanced Nuclear Power PlantJeong, Yeong Shin; Kim, Kyung Mo; Kim, In Guk; Bang, In CheolCONFERENCE19
2017-10Flow visualization and heat transfer performance of annular thermosyphon heat pipeKim, In Guk; Kim, Kyung Mo; Jeong, Yeong Shin; Bang, In CheolARTICLE869
2015-09-01Heat Removal Capacity of Heat Pipe Designs for In-Core Passive Decay Heat Removal SystemKim, Kyung Mo; Kim, In Guk; Jeong, Yeong Shin; Bang, In CheolCONFERENCE17
2015-10-30Heat Removal Performance of Hybrid Control Rod for Passive In-Core Cooling SystemKim, Kyung Mo; Jeong, Yeong Shin; Kim, In Guk; Bang, In CheolCONFERENCE14
2016-03Hybrid heat pipe based passive cooling device for spent nuclear fuel dry storage caskJeong, Yeong Shin; Bang, In CheolARTICLE1101
2015-08Hybrid heat pipe based passive in-core cooling system for advanced nuclear power plantJeong, Yeong Shin; Kim, Kyung Mo; Kim, In Guk; Bang, In CheolARTICLE672
Showing results 1 to 20 of 35

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