Keywords

Nuclear power plants, Data processing, Nuclear power plants, Safety measures

Abstract

A digital computer model has been developed to simulate the kinetic response of a thermal pressurized water reactor power plant. The program is capable of predicting core power and plant temperature variations which result from disturbances due to routine demand changes, control rod movement, and fission product poison transients as well as from transients during plausible accident situations. The development of the differential equations describing the influence of various primary plant components on the dynamics of the reactor have been heretofore documented in the literature. Finite difference equations facilitating the employment of a digital computer solution are fully derived. Confidence in program validity is supported by the simulation of previously studied accidents and comparison with the safety analyses of a licensed nuclear power generating plant. A source listing of the computer program is provided in the Appendix.

Notes

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Graduation Date

1978

Advisor

Wall, Donald B.

Degree

Master of Science (M.S.)

College

College of Engineering

Degree Program

Engineering

Format

PDF

Pages

84 p.

Language

English

Rights

Public Domain

Length of Campus-only Access

None

Access Status

Masters Thesis (Open Access)

Identifier

DP0013178

Subjects

Nuclear power plants -- Data processing, Nuclear power plants -- Safety measures

Collection (Linked data)

Retrospective Theses and Dissertations

Accessibility Status

Searchable text

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Included in

Engineering Commons

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