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Filtering by: Creator Al-Hussinie, Abdulaziz S. Subject Nuclear reactors -- Safety measures

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:

temperatures are below the boiling point of the coolant. Copyright° by Abdullah S. Al-Kheliewi