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Performance analysis of a long-life gas-cooled fast reactor using a modified Brayton cycle

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Gas-cooled fast reactors (GFRs) are one of the Generation IV nuclear reactor concepts developed to address future energy demands through sustainable, safe, and efficient power generation. This study aims to perform an integrated analysis of a long-life GFR capable of operating for 10 years without refuelling. This reactor core transfer its heat through a counter flow intermediate heat exchanger (IHX) into brayton cycle system to produce electricity or in co generation system. The Brayton cycle incorporating, reheat, regeneration, and bypass. The research methodology begins with a neutronic analysis using OpenMC, followed by thermodynamic analyses of heat transfer and energy conversion. The proposed reactor design remains critical throughout the 10-year operating period with an excess reactivity less than 7% dk/k at Np-237 mass 3.5% with average core power density is about 70W/cc.  The modified Brayton cycle achieves a thermal efficiency of 54% and a specific net work of 1550 kJ/kg. This study investigate some parametric survey of the IHX and the Brayton cycle optimization which include reheat, regeneration and bypass process.  These results demonstrate the feasibility of integrating a long-life GFR with an advanced Brayton cycle to achieve both high reactor performance and efficient energy conversion.
Title: Performance analysis of a long-life gas-cooled fast reactor using a modified Brayton cycle
Description:
Gas-cooled fast reactors (GFRs) are one of the Generation IV nuclear reactor concepts developed to address future energy demands through sustainable, safe, and efficient power generation.
This study aims to perform an integrated analysis of a long-life GFR capable of operating for 10 years without refuelling.
This reactor core transfer its heat through a counter flow intermediate heat exchanger (IHX) into brayton cycle system to produce electricity or in co generation system.
The Brayton cycle incorporating, reheat, regeneration, and bypass.
The research methodology begins with a neutronic analysis using OpenMC, followed by thermodynamic analyses of heat transfer and energy conversion.
The proposed reactor design remains critical throughout the 10-year operating period with an excess reactivity less than 7% dk/k at Np-237 mass 3.
5% with average core power density is about 70W/cc.
 The modified Brayton cycle achieves a thermal efficiency of 54% and a specific net work of 1550 kJ/kg.
This study investigate some parametric survey of the IHX and the Brayton cycle optimization which include reheat, regeneration and bypass process.
 These results demonstrate the feasibility of integrating a long-life GFR with an advanced Brayton cycle to achieve both high reactor performance and efficient energy conversion.

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