Steady thermal hydraulic analysis for a molten salt reactor

Steady thermal hydraulic analysis for a molten salt reactor 1 2 corresp first-author E-mail: dlzhang.xjtu@yahoo.com.cn E-mail: dlzhang.xjtu@yahoo.com.cn dlzhang.xjtu@yahoo.com.cn 1 2 2 1 2 State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an 710049, China State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an 710049, China School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, China School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, China The Molten Salt Reactor (MSR) can meet the demand of transmutation and breeding. In this study, theoretical calculation of steady thermal hydraulic characteristics of a graphite-moderated channel type MSR is conducted. The DRAGON code is adopted to calculate the axial and radial power factor firstly. The flow and heat transfer model in the fuel salt and graphite are developed on basis of the fundamental mass, momentum and energy equations. The results show the detailed flow distribution in the core, and the temperature profiles of the fuel salt, inner and outer wall in the nine typical elements along the axial flow direction are also obtained. Molten salt reactor Thermal hydraulics Steady characteristics Numerical simulation References Rosenthal M W , Kasten P R , Briggs R B . Nuclear Application & Technology , 1970 , 8 : 107 - 117 . Nuclear Application & Technology Dulla S , Ravetto P , Rostagno M M . Annals of Nuclear Energy , 2004 , 31 : 1709 - 1733 . Annals of Nuclear Energy Ignatiev V . MOSART fuels and container materials study: case for Na, Li, Be/F solvent system (2003b) , Proc. 2003 ANS/ENS International Winter Meeting (GLOBAL 2003) , New Orleans, USA . MOSART fuels and container materials study: case for Na, Li, Be/F solvent system (2003b) Merzlyakov V , Ignatiev V . Measurement of transport properties for molten Na,Li,Be/F mixture , the 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics , 2005 , Avignon, France . Measurement of transport properties for molten Na,Li,Be/F mixture Wang S . Molten salt related developments for SIMMER , the 12th International SIMMER Review Meeting , 2004 , Grenoble, France . Molten salt related developments for SIMMER Kondo S . Current status and validation of the SIMMER-III LMFR safety analysis code , Proc. ICONE-7 , 1999 , Tokyo, Japan . Current status and validation of the SIMMER-III LMFR safety analysis code Generation IV International Forum . A Technology Roadmap for Generation IV Nuclear Energy System, GIF-002-00 : 33 - 37 , 2002 . A Technology Roadmap for Generation IV Nuclear Energy System, GIF-002-00 Marleau G , Hebert A , Roy R . A user guide for DRAGON 3.05C , Institute de Genie Nuclearire, Department de Genie Physique, Ecole Polytechnique de Montreal , 2006 . A user guide for DRAGON 3.05C Jiri K , Ulrich G , Ulrich R . DYN1D-MSR dynamics code for molten salt reactors , Annals of Nuclear Energy , 2005 , 32 : 1799 - 1824 . DYN1D-MSR dynamics code for molten salt reactors Huang X Q , Gong D H , Li H . Journal of Guizhou University of Technology (Natural Science Edition) , 2001 , 30 : 9 - 12 . Journal of Guizhou University of Technology (Natural Science Edition) 10.1016/S1001-8042(08)60048-2 TL426 Supported by the National Natural Science Fundation of China (Grant No. 10575079) 2007-08-06 2008-06-20 2021-01-19 2008 Nuclear Science and Techniques 03 19