Analysis of Chinshan Unit 1 Full Load Rejection Transient Using RETRAN

E. Lin; Y. H. Cheng; J. K. Hsiue

doi:dx.doi.org/10.13182/NT81-A32783

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Home / Publications / Journals / Nuclear Technology / Volume 54 / Number 3

Analysis of Chinshan Unit 1 Full Load Rejection Transient Using RETRAN

E. Lin, Y. H. Cheng, J. K. Hsiue

Nuclear Technology / Volume 54 / Number 3 / September 1981 / Pages 380-384

First International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT81-A32783

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Full power generator load rejection transient initiated in startup test was simulated. The measured data are retrieved from STARTREC tape. The calculated and measured data especially for parameters of system pressure, core heat flux, feedwater flow rate, reactor water level, core flow, and normalized power are compared. The results indicate that the RETRAN code can successfully predict the parameters.