On-Line Simulation of Thermal Characteristics of Nuclear Fuel Rod by Electrically Heated Rod

Performance assessment of longitudinal flow through rod bundle arrangements using entropy generation minimization approach

“…The present analysis is based on the simplifying assumption of axially constant heat generation within the fuel core. Though it is not the case for an actual nuclear reactor conditions, it can be approximated for electrically heated fuel rod simulator [44,45]. 5.…”

Thermodynamic analysis of a solid nuclear fuel element surrounded by flow of coolant through a concentric annular channel

“…2 In actual practice the axial distribution of volumetric heat generation resembles a sinusoidal profile while the heat generation remains almost the same radially within a single fuel pin. But it can be approximated to a constant value for electrically heated fuel rod simulator (Soda, 1976). Since the primary objective of the present paper is to investigate the entropy generation behavior, a constant volumetric dissipation rate of energy inside fuel element has been assumed.…”