Index Catalog // ScholarsArchive@OSU

Start Over

Filtering by: Subject Nuclear reactors -- Safety measures -- Cost effectiveness 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:

Figure Page 1.1 SNAP-10 Nuclear Space Reactor 2 1.2 SP-100 Nuclear Space Reactor Configuration