Experimental studies and computational benchmark on heavy liquid metal natural circulation in a full height-scale test loop for small modular reactors
暂无分享,去创建一个
Yeji Kim | Il Soon Hwang | Jaehyun Cho | Yong-Hoon Shin | Ju-Eun Lee | Hyunyub Noh | Heejae Ju | Sungjune Sohn | I. Hwang | Jaehyun Cho | Ju-Eun Lee | Sungjune Sohn | Yeji Kim | Heejae Ju | Y. Shin | Hyunyub Noh
[1] B. Sehgal,et al. Experimental study on natural circulation and its stability in a heavy liquid metal loop , 2007 .
[2] Pavel Kudinov,et al. The TALL-3D facility design and commissioning tests for validation of coupled STH and CFD codes , 2015 .
[3] V. S. Stepanov,et al. Nuclear Power Development in Market Conditions with Use of Multi-purpose Modular Fast Reactors Svbr-75/100 , 2006 .
[4] H. Aït Abderrahim,et al. The MYRRHA ADS Project in Belgium Enters the Front End Engineering Phase , 2015 .
[5] Peter Baeten,et al. The MYRRHA ADS Project in Belgium Enters the Front End Engineering Phase , 2015 .
[6] Weimin Ma,et al. Transient experiments from the thermal-hydraulic ADS lead bismuth loop (TALL) and comparative TRAC/AAA analysis , 2006 .
[7] F. Huang,et al. Study on Pb-Bi natural circulation phenomena , 2005 .
[8] Feodor M. Mitenkov,et al. Small nuclear heat and power co-generation stations and water desalination complexes on the basis of marine reactor plants , 1997 .
[9] Pallippattu Krishnan Vijayan,et al. Natural circulation studies in a LBE loop for a wide range of temperature , 2016 .
[10] Mariarosa Giardina,et al. Analyses of single- and two-phase flow pressure drops in helical pipes using a modified RELAP5 code , 2012 .
[11] Washington,et al. RELAP5/MOD3 code manual: Code structure, system models, and solution methods. Volume 1 , 1995 .
[12] Kune Y. Suh,et al. The concept of proliferation-resistant, environment-friendly, accident-tolerant, continual and economical reactor (PEACER) , 2000 .
[13] Patrick R. McClure,et al. Lead–bismuth eutectic technology for Hyperion reactor , 2013 .
[14] K. Rehme. Pressure Drop Correlations for Fuel Element Spacers , 1973 .
[15] R. A. Seban,et al. Heat Transfer to a Fluid Flowing Turbulently in a Smooth Pipe With Walls at Constant Temperature , 1949, Journal of Fluids Engineering.
[16] Massimiliano Polidori,et al. Decay Heat Removal and Transient Analysis in Accidental Conditions in the EFIT Reactor , 2008 .
[17] Mariano Tarantino,et al. Heavy liquid metal natural circulation in a one-dimensional loop , 2011 .
[18] Kenneth C. Mills,et al. Equations for the Calculation of the Thermo-physical Properties of Stainless Steel , 2004 .
[19] Paride Meloni,et al. Benchmarking of thermal hydraulic loop models for Lead-Alloy Cooled Advanced Nuclear Energy System (LACANES), phase-I: Isothermal steady state forced convection , 2011 .
[20] 정승호. Development of an integral test loop, HELIOS and investigation of natural circulation ability for PEACER , 2006 .
[21] J. Kim,et al. Advanced passive design of small modular reactor cooled by heavy liquid metal natural circulation , 2015 .
[22] Xavier Ficquet,et al. International Congress on Advances in Nuclear Power Plants (ICAPP) , 2011 .
[23] D. F. Delmastro,et al. Phenomenology involved in self-pressurized, natural circulation, low thermo-dynamic quality, nuclear reactors: The thermal–hydraulics of the CAREM-25 reactor , 2013 .
[24] Fu Li,et al. Design aspects of the Chinese modular high-temperature gas-cooled reactor HTR-PM , 2006 .
[25] E. N. Sieder,et al. Heat Transfer and Pressure Drop of Liquids in Tubes , 1936 .
[27] N. D. Sylvester,et al. A Review of Explicit Friction Factor Equations , 1985 .
[28] Andreas G. Class,et al. Integral Circulation Experiment: Thermal–hydraulic simulator of a heavy liquid metal reactor , 2011 .