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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 | doi.org/10.13182/NT81-A32786
Articles are hosted by Taylor and Francis Online.
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.