Development Of Subchannel Analysis Code For Lead Cooled Fast Reactor Subassembly

In the situation of the world's increasing demand for energy and global warming,it is urgent to develop cleaner,safer,and more economical energy.In all non-greenhouse-gas-emitting sources,nuclear power generation is one of the top.This yields a significant reduction in the environmental impact of today's electricity generation.To continue this benefit,new systems will be needed to replace plants as they retire.Considering the requirements of nuclear energy in terms of safety,economy,sustainability,radioactive waste and fuel proliferation,the six most promising reactor types have been chosen for international R&D,lead-cooled fast reactor is one of these six types.In this paper,a subchannel analysis code has been developed for lead cooled fast reactor based on the current subchannel analysis code for pressurized water reactor.The physical parameters of lead,pressure drop correlation and heat transfer correlation which are suitable for wire-wrapped fuel assembly are added in the subchannel code.Then,the mixing coefficient has been obtained by calculating the temperature distribution of 7-rod assembly using both CFD software and subchannel analysis under the condition of both smooth rods and wire-wrapped rods.The ALFRED is calculated by using the subchannel code in this paper.The results are in good agreement with the design scheme,which verifies the accuracy and applicability of the code.Then,the subchannel analysis code is used to study the steady-state thermal-hydraulic calculation of subassembly model of the lead cold fast reactor core developed by the North China Electric Power University and the China Guangdong Nuclear Research Institute.The calculation yields the coolant outlet temperature,fuel and cladding temperature.The results show that the key thermal engineering parameters such as the maximum temperature of the fuel,the maximum temperature of the cladding and the outlet temperature of the coolant are less than the relevant safety limits and meet the design requirements.