Index Catalog // 蹄兔

清除筛选

筛选: 学科 Thermodynamics 学科 Nuclear reactors -- Safety measures

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

创造者:

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