Design features of advanced sodium-cooled fast reactor KALIMER-600

Proceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04

Volumn , Issue , 2004, Pages 637-645

  Hahn, Dohee ^a   Kim, Yeong Il ^a   Kim, Seong O ^a   Lee, Jae Han ^a   Lee, Yong Bum ^a  

^a Korea Atomic Energy Research Institute   (South Korea)

Author keywords

[No Author keywords available]

Indexed keywords

BREEDING BLANKETS; HEAT TRANSFER; NUCLEAR FUELS; SODIUM; STRUCTURAL DESIGN; TRANSPORT PROPERTIES; TRANSURANIUM ELEMENTS;

ELECTRICAL CAPACITY; LIQUID METAL REACTORS (LMR); NUCLEAR PROLIFERATION; SEISMIC ISOLATION; THERMAL DAMPING;

LIQUID METAL COOLED REACTORS;

EID: 14844300975     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (4)

1. S. G. Hong, et al., "Neutronic Design of KALIMER-600 Core with Moderator Rods," to be presented at this Conference.
2. D. Hahn, et al., "KALIMER Conceptual Design Report," KAERI Report, Korea Atomic Energy Research Institute TR-2204, May (2002)
3. H. Song, S. J. Kim, and Y. I. Kim, "Nuclear Design of A Na Cooled KALIMER-600 Core with No Blanket," Advances in Nuclear Fuel Management III (ANFM 2003), Hilton Head Island, South Carolina, USA (2003)
4. Y. M. Kwon, Y. B. Lee, W. P. Chang, D. Hahn, "SSC-K Code User's Manual (Rev.0)," KAERI/TR-1619/2000, Korea Atomic Energy Research and Institute (2000)