This thesis demonstrates a method of analog simulation of a Pressurized-Water Reactor (PWR) using simplified techniques. The simulation is for the reactor vessel and is patterned after the "Yankee," the PWR owned and operated by the Yankee Atomic Electric Company of Rowe, Massachusetts, and built by the Westinghouse Corporation of Pittsburgh, Pennsylvania. The entire analysis is based on the one group model (postulated that neutrons in the reactor are of one energy). The areas analyzed are: 1. Reactor kinetics - one delay group 2. Temperature effects on reactivity A. Fuel temperature coefficient B. Moderator and coolant temperature coefficient. 3. Control rod servo system The results of the program demonstrate that an effective simulation is possible using greatly simplified equations.
Library of Congress Subject Headings
Nuclear reactors; Nuclear engineering
Department, Program, or Center
Microelectronic Engineering (KGCOE)
Bartells, Philip, "Analysis of the Performance of the Pressurized-Water Nuclear Reactor by Electrical Simulation - Analog Computer" (1967). Thesis. Rochester Institute of Technology. Accessed from
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