Korean Development of Advanced Thermal-Hydraulic Codes for Water Reactors and HTGRs: Space and Gamma

Abstract The Korea nuclear industry has been developing the thermal-hydraulic system analysis Safety and Performance Analysis CodE (SPACE) and the GAs Multicomponent Mixture Analysis (GAMMA) code for safety analysis of pressurized water reactors (PWRs) and high-temperature gas-cooled reactors (HTGRs), respectively. SPACE will replace outdated vendor-supplied codes and will be used for the safety analysis of operating PWRs and for the design of an advanced PWR. SPACE consists of up-to-date physical models of two-phase flow dealing with multidimensional two-fluid, three-field flow. GAMMA consists of multidimensional governing equations consisting of the basic equations for continuity, momentum conservation, energy conservation of the gas mixture, and mass conservation of n species. GAMMA is based on a porous media model so that thermofluid and chemical reaction behaviors in a multicomponent mixture system and heat transfer within solid components, free and forced convection between a solid and a fluid, and radiative heat transfer between solid surfaces can be dealt with. GAMMA has a two-dimensional helium turbine model based on the throughflow calculation and a coupled neutronics-thermal-hydraulic model. Extensive code assessment has been performed for the verification and validation of SPACE and GAMMA.

[1]  Hyung Gon Jin,et al.  Stratified flow-induced air-ingress accident assessment of the GAMMA code in HTGRs , 2011 .

[2]  Kyung Doo Kim,et al.  DEVELOPMENT OF THE SPACE CODE FOR NUCLEAR POWER PLANTS , 2011 .

[3]  Ji Su Jun,et al.  THE BENCHMARK CALCULATIONS OF THE GAMMA+ CODE WITH THE HTR-10 SAFETY DEMONSTRATION EXPERIMENTS , 2009 .

[4]  Wolfgang Hoffelner,et al.  NUCLEAR ENERGY MATERIALS PREDICTION: APPLICATION OF THE MULTI-SCALE MODELLING PARADIGM , 2009 .

[5]  Hee Cheon No,et al.  Direct implementation of an axial-flow helium gas turbine tool in a system analysis tool for HTGRs , 2008 .

[6]  Hee Cheon No,et al.  Estimation of graphite density and mechanical strength variation of VHTR during air-ingress accident , 2008 .

[7]  Chang Keun Jo,et al.  Development of the CAPP Code Based on the Finite Element Method for the Analysis of VHTR Cores , 2008 .

[8]  Hee Cheon No,et al.  Multi-component diffusion analysis and assessment of GAMMA code and improved RELAP5 code , 2007 .

[9]  Hee Cheon No,et al.  A REVIEW OF HELIUM GAS TURBINE TECHNOLOGY FOR HIGH-TEMPERATURE GAS-COOLED REACTORS , 2007 .

[10]  Hee Cheon No,et al.  Experimental study on the reaction between nuclear graphite IG-110 and carbon dioxide , 2006 .

[11]  H. No,et al.  Experimental study on the oxidation of nuclear graphite and development of an oxidation model , 2006 .

[12]  Hee Cheon No,et al.  GAMMA Multidimensional Multicomponent Mixture Analysis to Predict Air Ingress Phenomena in an HTGR , 2006 .

[13]  H. No,et al.  Analysis of geometrical effects on graphite oxidation through measurement of internal surface area , 2006 .

[14]  Isao Kataoka,et al.  Correlations for the mass transfer rate of droplets in vertical upward annular flow , 2005 .

[15]  Hee Cheon No,et al.  Transient Multicomponent Mixture Analysis Baesd On an ICE Numerical Technique for the Simulation of an Air Ingress Accident in an HTGR , 2004 .

[16]  Thomas J. Hanratty,et al.  Correlation of entrainment for annular flow in horizontal pipes , 2002 .

[17]  S. Paras,et al.  Droplet entrainment and deposition in horizontal annular flow , 1991 .

[18]  Victor H. Ransom,et al.  A CHOKED-FLOW CALCULATION CRITERION FOR NONHOMOGENEOUS, NONEQUILIBRIUM, TWO-PHASE FLOWS , 1982 .

[19]  Robert E. Henry,et al.  The Two-Phase Critical Flow of One-Component Mixtures in Nozzles, Orifices, and Short Tubes , 1971 .

[20]  D. Chisholm.  A theoretical basis for the Lockhart-Martinelli correlation for two-phase flow , 1967 .

[21]  F. J. Moody,et al.  Maximum Flow Rate of a Single Component, Two-Phase Mixture , 1965 .