A Thermohydraulic Code for Low Temperature Nuclear Heating Reactor and Its Passive Residual Heat Removal Systems

References

• Andreas , G. 1991 . “Safety aspects of the 200 MWth siemens nuclear district heating plant,” . Nucl. Eng. Des. , 131 : 129 – 138 .
   Google Scholar
• Oleg , B. S. and Andrey , V. K. 1997 . “Nuclear district heat plants AST-500, present status and prospects for future in Russia,” . Nucl. Eng. Des. , 173 : 109 – 117 .
   Google Scholar
• Adamov , E. O. , Cherkashov , Y. M. Romenkov , A. A. 1997 . “Inherently safe pool-type reactor as a generator of low grade heat for district heating, air conditioning and salt water desalination,” . Nucl. Eng. Des. , 173 : 167 – 174 .
   Google Scholar
• Wang , D. Z. , Gao , Z. Y. and Zheng , W. X. 1993 . “Technical design features and safety analysis of the 200 MWt nuclear heating reactor,” . Nucl. Eng. Des. , 143 : 1 – 7 .
   Web of Science ®Google Scholar
• Wang , D. Z. 1993 . “The design characteristics and construction experiences of the 5 MWt nuclear heating reactor,” . Nucl. Eng. Des. , 143 : 19 – 24 .
   Web of Science ®Google Scholar
• Su , G. H. , Guo , Y. J. Zhang , J. L. “Steady and transient analysis and calculation of passive residual heat removed system,” . Proc. 3rd Int. Symp. of Multiphase Flow and Heat Transfer. Xi'an China . Vol. 2 , pp. 1025 – 1031 .
   Google Scholar
• Qiu , S. Z. , Zhou , T. Guo , Y. J. 1999 . “Modeling and dynamic simulation for emergency residual heat removal system of AC-600 (In Chinese),” . Chinese Nucl. Power Eng. , 20 : 143 – 147 .
   Google Scholar
• Su , G. H. 1997 . On the Density Wave Oscillation (Type I) of the Low Temperature Heating Reactor , Ph.D. thesis Xi'an Jiaotong University . [in Chinese]
   Google Scholar
• Su , G. H. , Jia , D. N. , Fukuda , K. and Guo , Y. J. 2001 . “Theoretical study on density wave oscillation of two-phase natural circulation under low quality conditions,” . J. Nucl. Sci. Technol. , 38 ( 8 ) : 607 – 613 .
   Web of Science ®Google Scholar
• Su , G. H. , Jia , D. N. , Fukuda , K. and Guo , Y. J. 2002 . “Theoretical and experimental study on density wave oscillation of two-phase natural circulation of low equilibrium quality,” . Nucl. Eng. Des. , 215 : 187 – 198 .
   Web of Science ®Google Scholar
• Zhou , T. 2002 . Development and Research on the Codes for Passive Residual Heat Removal Systems of Nuclear Heating Equipment,” , Ph.D. thesis Xi'an Jiaotong University . [in Chinese]
   Google Scholar
• Mcfadden , J. H. 1981 . RETRAN-02—A Program for Transient Thermohydraulic Analysis of Complex Fluid Flow systems, Vol. 1, Equations and Numeric , Idaho . EPRI-NP-1850-CCM
   Google Scholar
• Collier , J. G. 1981 . Convective Boiling and Condensation , New York : McGraw-Hill Book .
   Google Scholar
• Ma , Y. W. 1998 . Design and Utility of Air Cooler , Haerbin Industry University Press . [in Chinese]
   Google Scholar
• Weston , M. S. 2001 . Nuclear Reactor Physics , 146 John Wiley & Sons .
   Google Scholar
• Glasstone , S. and Alexander , S. 1963 . Nuclear Reactor Engineering , New York : Van Nostrand Reinhold .
   Google Scholar
• Du , S. H. 1992 . Nuclear Power Station , 85 – 86 . Beijing : Chinese Atomic Energy Press . [in Chinese]
   Google Scholar
• Swiss Federal Institute for Reactor Research . 1985 . Feasibility Study of the Swiss District Heating Reactor EIR-10 , Wurenlingen . PSI Report. HSK26/3
   Google Scholar
• Guo , Y. J. , Zhang , J. L. , Qiu , S. Z. Su , G. H. “MITARS— A thermal hydraulic analysis code for nuclear reactor system,” . Proc. 8th Int. Topical Meet. on Nuclear Reactor Thermal Hydraulics . Sept. 30-Oct. 4 1997 , Kyoto , Japan. Vol. 2 , pp. 1212 – 1219 .
   Google Scholar
• Guo , Y. J. 1994 . The Development and Applications of the Thermal-hydraulic Analysis Codes for Nuclear Power System , Ph.D. thesis Xi'an Jiaotong University . [in Chinese]
   Google Scholar
• INET . 1995 . Report of Institute of Nuclear Energy Technology (INET) in Tsinghua University [in Chinese]
   Google Scholar
• Jia , H. J. , Wu , S. R. Li , H. X. 2000 . “Thermalhydraulic inverstigation using a test facility simulating 200 MW integral heating reactor,” . J. Nucl. Sci. Technol. , 37 ( 2 ) : 202 – 208 .
   Web of Science ®Google Scholar
• Jia , H. J. , Jiang , S. Y. Xu , Y. H. 2001 . “Review of thermalhy-draulic experimental researches at INET,” . J. Nucl. Sci. Technol. , 38 ( 6 ) : 453 – 460 .
   Web of Science ®Google Scholar
• Shun , H. T. and Peng , M. Z. 1998 . “Analysis about residual heat process in 200MW heated reactor,” . Chinese Nucl. Power Eng. , 19 ( 1 ) : 21 – 25 . [in Chinese]
   Google Scholar