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

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

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...

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Bibliographic Details
Main Author: Al-Kheliewi, Abdullah S.
Other Authors: Klein, Andrew C.
Language:en_US
Published: 2012
Subjects:
Nuclear reactors > Safety measures
Thermodynamics
Thermonuclear fuels
Thermionic converters
Online Access:http://hdl.handle.net/1957/35507

Internet

http://hdl.handle.net/1957/35507

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