Abstract

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

Publication Date

7-1-1967

Document Type

Thesis

Department, Program, or Center

Microelectronic Engineering (KGCOE)

Advisor

Brown, George

Comments

Note: imported from RIT’s Digital Media Library running on DSpace to RIT Scholar Works. Physical copy available through RIT's The Wallace Library at: TK9145

Campus

RIT – Main Campus

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