Experimental validation of the TASS/SMR code for an integral type pressurized water reactor-Reference-Cited by-同舟云学术

Experimental validation of the TASS/SMR code for an integral type pressurized water reactor

Published:2008-10 Issue:10 Volume:35 Page:1903-1911
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Yang Soo Hyung,Chung Young-Jong,Kim Keung-Koo

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference18 articles.

1. SMART behavior under over-pressurizing accident conditions;Chang;Nucl. Eng. Des.,2000

2. Parametric studies on thermal hydraulic characteristics for transient operation for an integral type reactor;Choi;Nucl. Eng. Tech.,2006

3. Thermal hydraulic analysis of SMART for heat removal transients by a secondary system;Chung;Nucl. Eng. Des.,2003

4. Correlation equations for laminar and turbulent free convection from a vertical plate;Churchill;Int. J. Heat Mass Trans.,1975

5. Hwang, Y.D., Yang, S.H., Kim, S.H., Lee, S.W., Kim, H.K., Yoon, H.Y., Lee, G.H., Bae, K.H., Chung, Y.J., 2005. Model description of TASS/SMR code. Korea Atomic Energy Research Institute. KAERI/TR-3082/2005.

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