Investigation into the effects of a coastdown flow on the characteristics of early stage cooling of the reactor pool in KALIMER-600

Author:

Han Ji-Woong,Lee Tae-Ho,Eoh Jae-Hyuk,Kim Seong-O

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference10 articles.

1. Theoretical and experimental analysis of super phenix-1 thermohydraulic problems in natural convection;Astegiano,1981

2. Choi, S. K., 2005. Improvement on methodology for setting moment of inertia and coastdown flow in PHTS pump of KALIMER-600. LMR/FS200-ER-03-Rev.0/05(Internal Report).

3. Choi, B. Y., 2007. Thermal-hydraulic analysis in core catcher. LMR/FS100-AR-02-Rev.0/07(Internal Report).

4. Garner, P. L., Blomquist, R. N., Gelbard, E. M., 1992. COMMIX-1AR/P: a three-dimensional transient single-phase computer program for thermal hydraulic analysis of single and multicomponent systems, vol. 2, User’s Guide, ANL-92/33.

5. Han, J. W., Lee, T. H., Eoh, J. H., Kim, S. O., 2008. Investigation into thermal-hydraulic behavior in the KALIMER-600 Pool in a steady state, in: Transaction of Korean Nuclear Society Spring Meeting, pp. 61–62.

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