Abstract
Korea Electric Power Research Institute (KEPRI) developed real-time simulation Thermal hydraulic model (ARTS) which is based on the best-estimate code, RETRAN. It was adapted Kori unit 1 nuclear power plant analyzer (NPA). This paper describes the result of the some of steady and transient tests of the Kori unit 1 NPA. The simulated results are compared and reviewed with the plant data and calculated reference data. © Springer-Verlag Berlin Heidelberg 2005.
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CITATION STYLE
Lee, M. S., Seo, I. Y., Kim, Y. H., Lee, Y. K., & Suh, J. S. (2005). Transient test of a NSSS thermal-hydraulic module for the nuclear power plant simulator using a best-estimate code, RETRAN. In Lecture Notes in Artificial Intelligence (Subseries of Lecture Notes in Computer Science) (Vol. 3398, pp. 529–535). Springer Verlag. https://doi.org/10.1007/978-3-540-30585-9_59
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