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RETRAN Calculation of Loss of Feedwater Transients at Connecticut Yankee

D. P. Griggs, T. J. Honan

Nuclear Technology / Volume 54 / Number 3 / September 1981 / Pages 398-409

First International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT81-A32786

Northeast Utilities Service Company has performed sensitivity studies useful for modeling a loss of feedwater transient using the RETRAN code. These studies modeled the Connecticut Yankee Nuclear Power Plant, a four-loop Westinghouse pressurized water reactor. One-, two-, and three-volume steam generator secondary models were used in conjunction with a common primary side nodalization in a two-loop model. The importance of flow area of the steam generator secondary side for this transient has been investigated. A comparison of one-and two-loop models was made, along with an assessment of the differences in response between the equilibrium and nonequilibrium pressurizer models.