Thermal Power Calculation and Uncertainty Analysis of Large Pool Sodium-cooled Fast Reactor
Reactor nuclear power cannot be measured directly,and it can be represented by the value of the neutron fluence rate.Therefore,thermal power is adopted to calibrate reactor nuclear power in nuclear power plants.The coolant system of pool sodium-cooled fast reactor consists of three circuits of sodium-sodium-water,which is quite dif-ferent from that of pressurized water reactor(PWR).Due to the different configuration of the system,the calculation method of thermal power is also different from that of PWR.In this paper,the calculation method and uncertainty analysis of thermal power in large pool sodium-cooled fast reactor is analyzed,which is used to calibrate the nuclear power measuring instrument of reactor.The results show that for large pool sodium-cooled fast reactor,the uncertainty of thermal power calculation is within the conservative assumption of the initial power of accident analysis,the result of thermal power of core mainly depends on the power of steam generator,and the influence of other factors on the final calculation is less than 1%.
sodium cooled fast reactorthermal poweruncertainty
万方数据
维普
