References
- Hahn , D. H. 2002 . KALIMER Conceptual Design Report , Korea Atomic Energy Research Institute (KAERI) . KAERI/TR-2204/2002
- Park , J. H. 1998 . Development of the SPIKE code for Analysis of the Sodium Water Reaction , Korea Atomic Energy Research Institute (KAERI) . KAERI/TR-1123/98
- Hori , M. 1980 . “Sodium/water reactions in steam generators of liquid metal fast breeder reactors,” . At. Energy Rev.-Austria , 18 ( 3 ) : 707 – 778 .
- Greene , D. A. 1972 . “Steam generator vessel pressures resulting from a sodium/water reaction: a computer analysis with the SWEAR code,” . Nucl. Technol. USA , 14 ( 3 ) : 218 – 231 .
- Vambenepe , G. “Liquid metal fast breeder reactor steam generator survey of the consequences of large scale sodium water reaction,” . ENS/ANS Int. Topical Meeting on Nuclear Power Reactor Safety . Oct. 16–19 1978 , Brussels , Belgium.
- Kim , Y. S. , Sim , Y. S. Kim , E. K. 2002 . “Evaluation of the SWR's early pressure variations in the KALIMER IHTS,” . J. Energy Eng. , 11 ( 2 ) : 122 – 129 .
- Eoh , J. H. , Sim , Y. S. Kim , Y. S. “Assessment of analysis model for longer-term effects of SWR in LMR,” . Proc. Korean Nuclear Society (KNS), 2001 Spring Meeting . May 23–25 2001 , Che-Ju , Korea.
- Nahvandi , A. N. and Rashevsky , M. 1962 . Computer Program for Critical Flow Discharge of Two Phase Steam-Water Mixtures , Westinghouse Electric Corporation, Atomic Power Division . CVNA-128
- Eoh , J. H. , Kim , E. K. and Kim , S. O. “Development of tube leak model for analysis code of SWR in LMR,” . Proc. Korean Nuclear Society (KNS), 2002 Autumn Meeting, Yong-Pyong . Oct. 23–25 2001 , Korea .