Research On Making Continuous Energy Point Cross Section Library And Burnup Library Of Key Nuclides For Lead-based Fast Reactor

Lead-based fast reactor(lead cooling or lead bismuth cooling)is one of the important alternatives of the fourth generation of nuclear power system officially released by GIF.It has special advantages in terms of safety,economy and feasibility.The neutron spectrum of Pb based fast reactor is significantly different from that of traditional PWR,and the physical properties of nuclide in core are different.For example,the reaction section and radionuclide neutron nuclide fission yield value,numerical will change greatly,and as the lead bismuth coolant nuclide volume occupied a larger share,compared with the traditional pressurized water reactor,the data of the key nuclides,Pb,Bi and some actinides need to be considered in the core calculation of the lead based fast reactor.In this paper,the database of Monte Carlo code named cosRMC adapted to lead-based fast reactor were made using the data of these key nuclides in lead-based fast reactor from the different international nuclear data evaluation libraries,mainly including ENDF/B-?.1,JENDL-4.0,JEFF-3.2 and BROND-3.1,which contain continuous energy cross section library and yield database.The format of the database of the cosRMC program is in the same format as the PWR database.For the continuous energy point section library,we used NJOY code to make continuous point cross section data at 300K.The cross section data at other temperature points were made by SIGACE program.For fission yield database,we used the fission yield data in ENDF/B-?.1(500KeV)to update the fission yield data of nuclides induced by thermal neutron in the original database,so as to make the new fission yield database better applicable to the burnup calculation of fast reactors.After the completion of the database,some typical fast reactor benchmarks in the world are used to verify and analyze them.The study found that results of new database consistent with the benchmark results.The computation accuracy of Pb and Bi continuous point cross section is equivalent using ENDF/B-VII.1,JENDL-4.0,JEFF-3.2 and BROND-3.1 database,but the accuracy of Pb and Bi continuous point section produced by BROND-2.2 evaluation library is poor.The results using new fission yield database and thermal neutron library before show that the difference of effective multiplication factor of RBEC-M between the beginning and the ending is about 100pcm,but for some nuclides such as 133Cs,96Zr? 131Xe and others,production changes are more than 10%;For OECD-NEA benchmark,the consumption of fuel between the beginning and the ending is the same,while for 133Cs,131Xe,128Te and so on,production changes are more than 10%.