Nuclear Engineering ETDs

Publication Date

12-15-1975

Abstract

The reactor described herein is aimed at developing an accurate physical model for axial power shaping studies in pressurized water reactors of the current generation. The model is also intended for numerical studies on: (1) reactor load-follow capability throughout a fuel loading lifetime; and (2) burnup dependence of the reactor stability against axial xenon oscillations. Accordingly, a proper account of the concerned physical phenomenology was sought. The results reported herein solely concern methods development and assessment.

A one-dimensional (axial) core geometrical model, coupled with

fuel temperature-and moderator coolant thermal-hydraulics-feedback was assembled. Algorithms for computing the feedback effects were developed and incorporated into a general purpose diffusion-theory-depletion computer program (CITATION). The handling of Doppler feedback is based upon the space-dependent average fuel temperature and the functional dependence of fuel nuclide cross sections on the fuel temperature. The handling of the moderator thermal-hydraulics feedback is circumscribed by the subcooled regime. Constant coolant pressure and mass flow rate are assumed. The associated spectral effects are accounted for.

Document Type

Dissertation

Language

English

Degree Name

Nuclear Engineering

Level of Degree

Doctoral

Department Name

Nuclear Engineering

First Committee Member (Chair)

Robert Leroy Long

Second Committee Member

Glenn Alan Whan

Third Committee Member

Ronald Allen Knief

Fourth Committee Member

Surendra N. Purohit

Fifth Committee Member

R. Douglas O'Dell

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