الفهرس 
INTRODUCTIONOnly 14 pages are availabe for public view
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Abstract
Fully Ceramic Microencapsulated (FCM) fuel is one of the most advanced fuel types for the next nuclear reactor generations. The TRISO particles that make up the FCM fuel structure are embedded in a SiC matrix. Due to their excellent design and low power density, Small Modular Reactors (SMRs) have exceptional inherent safety. Combining FCM fuel and SMR could make the reactor safer. ATFs (Accident Tolerant Fuels) can improve nuclear power plant safety by improving its performance during normal operation, transient situations, and accident scenarios, as well as providing longer accident response time. In this work, the neutronic and thermal hydraulics of a SMART reactor were examined, and the performance of FCM (UC) loaded into the core was contrasted with that of conventional UO2 fuel. The effective multiplication factor and burnup were investigated as part of the neutronic assessment of the SMART core specification, and the results are presented along with a review of the attributes and potential benefits. Compared to uranium dioxide fuel, uranium carbide fuel offers the advantages of mechanical stability, improved thermal conductivity, and high fuel density. Both UC and conventional fuel (UO2) have the same melting point. As a result, under reactor operating conditions, UC has better safety margins. We also utilized various cladding, including (FCM -Zircaloy, FCM -FeCrAl, FCM -combining of zircaloy and FeCrAl). The neutronic parameters were estimated using the stochastic MCNPX 2.6 code. The annual reload requirement was met with high fuel enrichment. We compared the performances of special designs of the FCM fuel to the conventional fuel during normal operation and anticipated operational occurrences. The neutronic safety parameters, such as temperature reactivity coefficients, power peaking factor, effective delayed neutron fraction and generation time, determine the reactor dynamic response. Therefore, assessment of reactor behavior throughout the operational cycle is a key factor in reactor safety analysis for transient conditions. We analyzed the thermal hydraulic performance of SMART reactor, and compared the results to conventional UO2 fuel. MATLAB and RELAP5 were used to carry out the thermal hydraulic analysis of FCM designed cases with successful neutronic safety parameters. We simulated the reactor dynamics based on point kinetics and lumped parameters thermal hydraulic model. A ramp input reactivity was inserted into the core and the behavior of both fuel types was analyzed. The homogenized thermal properties of the FCM-UC fuel rods were evaluated using the volume fraction of the material (volumetric average model). Because they are safer and more advantageous than normal uranium oxides, we observed that Fully Ceramic Microencapsulated - Uranium Carbide (FCM-UC) fuel type is more attractive. This work may offer recommendations for future optimized designs of the SMART reactor parameters.