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Filtering by: Committee Member Piatt, John F. Creator Al Kheliewi, Abdullah S.

Modeling transient thermalhydraulic behavior of a thermionic fuel element for nuclear space reactors

Creator:

Al-Kheliewi, Abdullah S.

Abstract:

A transient code (TFETC) for calculating the temperature distribution throughout the radial and axial positions of a thermionic fuel element (TFE) has been successfully developed. It accommodates the variations of temperatures, thermal power, electrical power, voltage, and current density throughout the TFE as a function of time as well as...

Resource Type:

Dissertation

Full Text:

committee members: Dr. Jack F. Higginbotham, Dr. M. M. Kulas, and Dr. John Peterson for their time and