Abstract
In this work, the feasibility of employing “Single Flow Channel Analysis†technique for obtaining the thermal-hydraulic behavior of a TRIGA Mark II research reactor has been studied. Two different simulation methods have been investigated for this purpose; one in which there is no variation in volumetric heat generation along the fuel axis and the other in which there is variation. A hot rod factor of 1.70 has been taken. Results obtained from simulation methods have been compared with both theoretical results and experimental data provided by the manufacturers. Results show that data generated from both simulation methods are more accurate compared to theoretical calculations. Also, the simulation method exempting variation of heat generation has predicted maximum temperature of the fuel centerline just above 750 oC, which is sufficiently accurate. However, temperatures obtained at different axial and radial locations are not close to the experimental values. On the other hand, the simulation technique in which variation of heat generation exists has been able to provide temperature profiles inside the fuel rod and cladding surface almost identical to the experimental values. However, temperature profile of the fuel outer surface is found to be quite different from experimental values. Â
Highlights
Unlike power reactors, research reactors are specially designed nuclear reactors that are to be used for research purpose only
The first geometry consists of a single fuel element which has a volumetric heat generation rate equal to the average value of the same in the TRIGA Mark II research reactor fuel
The fuel element has been divided into 13 segments, similar to fuel pellets in real situation, each having different values of volumetric heat generation rate
Summary
Research reactors are specially designed nuclear reactors that are to be used for research purpose only. TRIGA Mark-II is one of the design variations of the TRIGA research reactor types Till date, this model is operational in multiple countries. This model is operational in multiple countries This reactor has been used for a variety of research works and scientific studies, both experimental and numerical. Žerovnik et al studied the use of multiple detectors on the measurement of thermal power of a TRIGA Mark II research reactor [9]. El-Bakkari et al conducted a fuel burnup analysis for TRIGA research reactor using Monte-Carlo nuclear code [14]. An attempt has been made to find out the feasibility of using single flow channel analysis technique for simulating the thermal behavior of the fuel rod inside a TRIGA Mark II reactor core. In order to do so, the results from the simulation methods have been compared with results from theoretical analysis as well as experimental data
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