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Selected Papers from the Fifth NTHAS SymposiumMoo Hwan Kim aa Department of Mechanical Engineering , Pohang University of Science and Technology ,South KoreaPublished online: 07 Oct 2011.

To cite this article: Moo Hwan Kim (2008) Selected Papers from the Fifth NTHAS Symposium, Heat Transfer Engineering, 29:8,657-658, DOI: 10.1080/01457630801980558

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Heat Transfer Engineering, 29(8):657–658, 2008Copyright C©© Taylor and Francis Group, LLCISSN: 0145-7632 print / 1521-0537 onlineDOI: 10.1080/01457630801980558

editorial

Selected Papers from the FifthNTHAS Symposium

MOO HWAN KIMDepartment of Mechanical Engineering, Pohang University of Science and Technology, South Korea

The Fifth Korea-Japan Symposium on Nuclear Thermal Hy-draulics and Safety (NTHAS5) was hosted in Jeju Island, SouthKorea, from November 26–29, 2006. In the hopes of contribut-ing a nuclear system with enhanced safety, a biennial sym-posium program was initiated across the sea by the thermal-hydraulics divisions of the Atomic Energy Society of Japan(AESJ) and the Korean Nuclear Society (KNS). The first sym-posium (NTHAS1), held at Busan, Korea, from October 21–24, 1998, was a great success, attracting seventy papers fromKorea and thirty papers from Japan. The second to fourth sym-posiums were held in Fukuoka (2000), Gyeongju (2002), andSapporo (2004), respectively, with great success in technicalquality and a multitude of participants. The fifth symposiumwas also very successful, with more than 100 papers and 150participants. Also, the “Korea-Japan Joint Summer School 2006on Experimental Thermal Hydraulics, Advanced ComputationalFluid Dynamics, Industrial Applications and Issues on FutureTechnologies for Students and Young Researchers” was heldjust before this symposium to enhance the technical knowledgetransfer from experienced researchers to a younger generation.

Current issues regarding energy and environment such asglobal warming are major challenges of this century. Consid-ering the availability of energy resources and impact on globalenvironment, nuclear energy may be the most reasonable choicecurrently available. The economic competitiveness of nuclearenergy with enhanced safety is the most important concern topromote this promising energy source. With the introductionof evolutionary and revolutionary concepts around the globe,

Address correspondence to Prof. Moo Hwan Kim, Department of Mechani-cal Engineering, Pohang University of Science and Technology, San 31, Hyoja-dong, Pohang, 790-784, South Korea. E-mail: mhkim@postech.ac.kr

including the so-called “Generation IV Nuclear Energy Sys-tems,” multilateral R&D opportunities are becoming more im-portant in the areas of thermal-hydraulics and safety. To discussthese areas, the honorary lectures by Prof. A. Serizawa at KyotoUniversity—four plenary lectures, eight keynote lectures, andthe following sessions—were prepared:

• thermal hydraulics fundamentals• two-phase flow experiment and analysis• computational fluid dynamics and heat transfer• CHF and post-CHF heat transfer• instrumentation and measurement techniques• water reactor thermal hydraulics and safety• liquid metal reactor thermal hydraulics and safety• gas-cooled reactor thermal hydraulics and safety• safety analysis and code development• fusion reactor thermal hydraulics and safety• fluid structure interaction• supercritical fluid heat transfer• severe accident experiment and analysis• thermal hydraulics aspects of plant operation• heat exchanger design and turbo machinery

For this special issue of Heat Transfer Engineering, the bestpaper has been recommended by the chairmen at each session.Then, eleven manuscripts have been selected by the scientificcommittee.

The first paper, “Transient Behavior of Gas EntrainmentCaused by Surface Vortex” by Ezure et al., describes the gasentrainment due to surface vortex and its transient phenomena.Time trends of circulation and length of gas core for the inter-mittent surface vortices were measured by the particle imagevelocimetry and visualization.

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658 M. H. KIM

The second paper, “Development of a Multi-DimensionalFluid Dynamics Code and Its Benchmarking for the SubcooledBoiling Flow” by Bae et al., indicates that the implementationof the interfacial area concentration transport equation into thecode is essential for the analysis of two-phase flow.

The third paper, “Head Loss Coefficient Evaluation Basedon CFD Analysis for PWR Downcomer and Lower Plenum”by Jeong et al., shows that the pressure drop calculated by thecommercial CFD code across downcomer and lower plenum,which have very complicated geometry, appears to be in goodagreement with the data in engineering calculation note.

The fourth paper, “Critical Heat Flux Tests for an Applicationof the Three-Pin Fuel Test Loop in HANARO” by Choi et al.,presents the test results of the critical heat flux of a three rodbundle in HANARO (High-flux Advanced Neutron ApplicationReactor).

The fifth paper, “The Experimental Study on Mixing Charac-teristics in a Square Sub-Channel Geometry with Typical FlowDeflectors” by Chang et al., describes the lateral flow struc-tures in a sub-channel geometry with two types of flow deflec-tors: a conventional split type mixing vane and a swirl typevane that has been designed to enhance the swirling flow in asub-channel.

The sixth paper, “Thermal Feasibility Analyses for 1356MWeHigh Conversion Type Innovative Water Reactor for FlexibleFuel Cycle” by Liu et al., introduces a new reactor concept ofinnovative water reactor for a flexible fuel cycle, which is underdevelopment at the Japan Atomic Energy Agency. The thermalfeasibility of this reactor core is studied by using a modifiedtransient analysis code TRAC-BF1.

The seventh paper, “Evaluation Method for Flow AcceleratedCorrosion of Components by Corrosion Analysis Coupled withFlow Dynamics Analysis” by Naitoh et al., introduces the cor-rosion analysis models combined with three-dimensional flowdynamics and heat transfer analysis models to evaluate corrosiondamage.

The eighth paper, “Validation of Analytical Capabilities ofRELAP/MOD3.3 on Boron Dilution during SBLOCA and Lossof Residual Heat Removal System” by Kasahara, presents the

analysis results for the OECD/PKL experiments on boron dilu-tion. A focus is set on both the correct prediction of the thermal-hydraulic parameters and the boron dynamics in the pressurizedwater reactor system.

The ninth paper, “Proposal of Design Criteria for Gas En-trainment from Vortex Dimples Based on a Computational FluidDynamics Method” by Sakai et al., describes the design criteriafor gas entrainments from the liquid surface in a fast breederreactor system. Based on CFD calculations for elemental ex-periments of the surface vortex, local CFD non-dimensionalnumbers were defined as the design criteria to prevent gasentrainments.

The tenth paper, “The Effect of Material Composition on theStrength of a Steam Explosion” by Song et al., and the eleventhpaper, “Steam Explosion Experiments Using Nuclear ReactorMaterials in the TROI Facilities” by Kim et al., present the newfindings of steam explosion from a series of TROI experimentsat Korea Atomic Energy Research Institute.

The next Korea-Japan Symposium on Nuclear Thermal Hy-draulics and Safety (NTHAS6) is scheduled to be held in theIslands of Okinawa, Japan, November 24–27, 2008. We wouldlike to invite the readers to discuss up-to-date technical infor-mation for nuclear thermal hydraulics and safety and provide aunique opportunity to interact with colleagues from Japan andKorea.

Moo Hwan Kim is a professor of the departmentof mechanical engineering at the Pohang Uni-versity of Science and Technology (POSTECH),South Korea. He received his Ph.D. from Univer-sity of Wisconsin-Madison. He has been teach-ing at POSTECH since 1987. He specializes inphase change heat transfer and nuclear thermalhydraulics. Recently, he has been interested innanofluids and boiling in a microchannel. Heserved as a program director for nuclear technol-

ogy program at Korea Science and Engineering Foundation and is a memberof Korea Nuclear Council. He has worked as the chair of the technical pro-gram committee for NTHAS 5. He is also an associate editor for Heat TransferEngineering.

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