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Fuel Performance Comparison of Uranium Nitride and Uranium Carbide in VVER-1200 using OpenMC /

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dc.contributor.author Jamil, Meekal
dc.date.accessioned 2024-12-30T07:55:53Z
dc.date.available 2024-12-30T07:55:53Z
dc.date.issued 2024-12
dc.identifier.other 361624
dc.identifier.uri http://10.250.8.41:8080/xmlui/handle/123456789/48683
dc.description Supervisor: Dr. Majid Ali en_US
dc.description.abstract Nuclear power is a reliable and large-scale source of GHG-free electricity. This study asses the viability of ATF fuel of uranium nitrate (UN) and uranium carbide (UC) as fuel for the VVER-1200 reactor. A comprehensive literature review has been conducted on the current state of global nuclear power and fuels. An in-depth overview of the VVER-1200 and Accident Tolerant fuels is presented and a review of the development of ATFs identified UN and UC as viable fuels for the VVER reactor. The study utilizes OpenMC to model the VVER-1200 core and compares the behaviour of ATF with conventional fuel. Key findings include comparable k-eff values implying similar neutronic behaviour. UO2 and UC showed similar fission rates across the core while UN showed higher neutron flux and fission rate in the outer part of the core. The base Z44B2 showed increased flux and fission rate with UN as the fuel. ATF behaviour showed to be comparable to the UO2 and thus is a potential alternative to conventional fuels. ATFs provide an additional level of safety because of higher melting points and higher thermal conductivity. This study can be further improved to investigate the depletion of ATFs so that the behaviours of the core over large periods of time, fission products and operator safety can be assessed. Base case k-eff value of 1.24795 are comparable to k-eff values generated by UN and UC. en_US
dc.language.iso en en_US
dc.publisher U.S.-Pakistan Center for Advanced Studies in Energy (USPCASE) en_US
dc.relation.ispartofseries TH-602;
dc.subject Nuclear Power en_US
dc.subject VVER en_US
dc.subject Uranium Nitride (UN) en_US
dc.subject MS ESE Thesis en_US
dc.title Fuel Performance Comparison of Uranium Nitride and Uranium Carbide in VVER-1200 using OpenMC / en_US
dc.type Thesis en_US


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