Numerical study on thermo-hydrodynamics in the reactor internals of SMART

Nuclear Engineering and Design

Volumn 241, Issue 7, 2011, Pages 2536-2543

  Kim, Kyung Min ^a   Lee, Byoung In ^a   Cho, Hyung Hee ^a   Park, Jin Seok ^b   Chung, Young Jong ^b  

^a Yonsei University   (South Korea)

^b Korea Atomic Energy Research Institute   (South Korea)

Author keywords

[No Author keywords available]

Indexed keywords

BROKEN DOWN; COMMERCIAL CODES; FLOW-MIXING; HOT FLOW; NOMINAL OPERATIONS; NUMERICAL STUDIES; PRESSURE AND TEMPERATURE; REACTOR INTERNALS; TEMPERATURE RANGE; THERMOHYDRODYNAMICS;

DESCALING; NUCLEAR PROPULSION; NUCLEAR REACTORS; STEAM; STEAM GENERATORS;

INLET FLOW;

EID: 79958127975     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2011.04.032     Document Type: Article

References (15)

1. K.H. Bae, H.C. Kim, M.H. Chang, and S.K. Sim Safety evaluation of the inherent and passive safety features of the smart design Annals of Nuclear Energy 28 2001 333 349 (Pubitemid 32033773)
2. S. Becker, and E. Laurien Three-dimensional numerical simulation of flow and heat transport in high-temperature nuclear reactors Nuclear Engineering and Design 222 2003 189 201
3. M.H. Chang, and S.H. Kim The Republic of Korea's R&D Program and activities for nuclear desalination Proceedings of A Symposium on Desalination of Seawater (IAEA) Taejon, Korea, May 26-30 1997
4. M.H. Chang, S.K. Sim, and D.J. Lee SMART behavior under over-pressurizing accident conditions Nuclear Engineering and Design 199 2000 187 196
5. Y.-J. Chung, S.W. Lee, and H.-C. Kim Thermal hydraulic analysis of SMART for heat removal transients by a secondary system Nuclear Engineering and Design 225 2003 257 270
6. Y.-J. Chung, S.W. Lee, H.-C. Kim, and S.-Q. Zee Thermal hydraulic calculation in a passive residual heat removal system of the SMART-P plant for forced and natural convection conditions Nuclear Engineering and Design 232 2004 277 288
7. Y.-J. Chung, S.H. Kim, B.-D. Chung, M.-K. Chung, and S.-Q. Zee Two phase natural circulation and the heat transfer in the passive residual heat removal system of an integral type reactor Annals of Nuclear Energy 33 2006 262 270 (Pubitemid 43227553)
8. Y.-J. Chung, S.W. Lee, S.H. Kim, and K.K. Kim Passive cool down performance of a 65 MW integral reactor Nuclear Engineering and Design 238 2008 1681 1689
9. W.K. In, D.H. Hwang, Y.J. Yoo, and S.Q. Zee Assessment of core protection and monitoring systems for an advanced reactor SMART Annals of Nuclear Energy 29 2002 609 621
10. K.M. Kim, B.I. Lee, H.H. Cho, K.R. Kim, and J.S. Park Thermo-hydraulic analysis for evaluating flow induced loads in the SMART reactor Proceedings of KSME Annual Spring Meeting 2010, Seoul, Korea, May 28 2010
11. S.W. Lee, S.H. Kim, and Y.J. Chung Development and steady state level experimental validation of TASS/SMR core heat transfer model for the integral reactor SMART Annals of Nuclear Energy 36 2009 1039 1048
12. M.F. Robbe, M. Lepareux, E. Treille, and Y. Cariou Numerical simulation of a Hypothetical Core Disruptive Accident in a small-scale model of a nuclear reactor Nuclear Engineering and Design 223 2003 159 196
13. C.T. Tran, P. Kudinov, and T.N. Dinh An approach to numerical simulation and analysis of molten corium coolability in a boiling water reactor lower head Nuclear Engineering and Design 240 2010 2148 2159
14. S.H. Yang, Y.-J. Chung, and H.C. Kim Assessment of the MDNBR enhancement methodologies for the SMART control rods banks withdrawal event Annals of Nuclear Energy 32 2005 1567 1583 (Pubitemid 41203567)
15. S.H. Yang, Y.-J. Chung, and S.Q. Zee Safety analysis for an inadvertent control rod withdrawal event during a power operation of an advanced integral reactor Nuclear Engineering and Design 237 2007 1060 1070 (Pubitemid 46589547)