Passive cooldown performance of a 65 MW integral reactor

Nuclear Engineering and Design

Volumn 238, Issue 7, 2008, Pages 1681-1689

  Chung, Young Jong ^a   Lee, Seong Wook ^a   Kim, Soo Hyoung ^a   Kim, Keung Koo ^a  

^a Korea Atomic Energy Research Institute   (South Korea)

Author keywords

[No Author keywords available]

Indexed keywords

COOLING SYSTEMS; NUCLEAR ENERGY; SENSITIVITY ANALYSIS; THERMAL EFFECTS;

PASSIVE COOLDOWN; SHUTDOWN COOLING SYSTEM (SCS); THERMAL POWER;

NUCLEAR REACTORS;

EID: 43049162140     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2007.12.008     Document Type: Article

References (12)

1. Chang, M.H., Yeo, J.W., Zee, S.Q., Lee, D.J., Park, K.B., Koo, I.S., Kim, H.C., Kim, J.I., 2002. Basic design report of SMART, KAERI/TR-2142/2002, KAERI, Daejon, Korea.
2. Chexal B., Lellouche G., Horowitz J., and Healzer J. A Void fraction correlation for generalized applications. Prog. Nucl. Energy 27 4 (1992) 255-295
3. Choi K.-Y., Park H.-S., Cho S., Park C.-K., Lee S.-J., Song C.-H., and Chung M.-K. VISTA: thermal hydraulic integral test facility for the SMART reactor. Proceedings of the 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURRETH-10). Seoul, Korea, October 5-9 (2003)
4. Chung Y.-J., Kim H.-C., Chung B.-D., Chung M.-K., and Zee S.-Q. Two phase natural circulation and heat transfer in the passive residual heat removal system of an integral type reactor. Ann. Nucl. Energy 33 (2006) 262-270
5. Humphries, J.R., Davies, K., 1998. A floating desalination/co-generation system using the KLT-40 reactor and Canadian RO desalination technology. IAEA-TECDOC-1172, Obninsk, Russia, July 20-24.
6. Hwang, Y.D., Yang, S.H., Kim, S.H., Lee, S.W., Kim, H.K., Yoon, H.Y., Lee, G.H. Bae, G.H., Chung, Y.J., 2005. Model description of TASS/SMR code. KAERI/TR-3082/2005, KAERI, Daejon, Korea.
7. Ichihara Y. A perspective on nuclear power generation in the future electric power industry for nonspecialists in the electric power related industries. Proc. IEEE 89 12 (2001) 1793-1807
8. Jeong J.J., Ha K.S., Chung B.D., and Lee W.J. Development of a multi-dimensional thermal hydraulic system code. MARS 1.3.1. Ann. Nucl. Energy 26 (1999) 1611-1642
9. Kim, H.K., 2007. TASS/SMR verification report using VISTA natural circulation experiment, KAERI internal report, KAERI, Daejon, KOREA.
10. Kim S.-H., Kim K.K., Yeo J.W., Chang M.H., and Zee S.Q. Design verification program of SMART. Proceedings of the GENES4/ANP2003. Kyoto, Japan, September 15-19 (2003)
11. Misra B.M., and Kupitz J. The role of nuclear desalination in meeting the potable water needs in water scarce areas in the next decades. Desalination 166 (2004) 1-9
12. Nisan S., Caruso G., Humphries J.-R., Mini G., Naviglio A., Bielak B., Asuar Alonso O., Martins N., and Volpi L. Sea-water desalination with nuclear and other energy sources: the EURODESAL project. Nucl. Eng. Des. 221 (2003) 251