Development Of Proton-neutron Coupling Transport And Burnup Calculation Code For Accelerator Driven Sub-critical System

Partitioning and Transmutation strategy can effectively reduce the radioactive hazards of nuclear reactor waste,and significantly reduce the storage volume and time in geological disposal of high-level radioactive waste,which is a powerful solution to the reprocessing of reactor spent fuel.Accelerator Driven Sub-critical Systems(ADS)is recognized as the most effective nuclear waste transmutation device in the world.In ADS system,the high-energy proton beams bombard with heavy metal spallation target,then the generated spallation neutrons will drive the sub-critical reactor and maintain the nuclear fission process,so the minor actinide nuclides and long-lived fission product nuclides can be transmuted effectively.The target-reactor coupling physics calculation is the basis of parameter design and scheme analysis for ADS system.In this paper,a self-designed proton-neutron coupled transport and burnup code system are developed for accelerator driven sub-critical system,which provides an effective analysis tool for the physical calculation of ADS target-reactor system.In this paper,the target-reactor coupling analysis method based on spallation reaction code and Open MC is explored firstly,and the hybrid high-energy neutron cross section library IMPC-ADS fabricated by NJOY2016 code is also applied in the target-reactor coupled calculation.The correctness of IMPC-ADS library is verified by ICSBEP critical benchmark problem,fixed source of Godiva sphere and neutronics analysis of Ci ADS sub-critical reactor.Then,OECD-ADS target reactor model is used to verify the feasibility of this target-reactor coupling method.Next,in order to perform burnup analysis in ADS target-reactor coupled calculation,a new point depletion code IMPC-Depletion1.0 is developed firstly based on the TTA and CRAM algorithm.The code can be applied to decay,constant flux and constant power irradiation calculation.The results of IMPC-Depletion1.0 are in good agreement with those of other reference codes.Then based on Python3.6 and IMPC-Depletion1.0,transport-burnup calculation code system IMPC-Burnup2.0 is developed to perform the ADS burnup analysis.In IMPC-Burnup2.0 code,the external neutron source simulated by spallation reaction code will be converted into HDF5 format for neutron transport Monte Carlo code Open MC firstly,then the depletion solver IMPC-Depletion1.0 is invoked to update material composition in each burnup cells.In addition,the BOS algorithm and PC prediction-correction algorithm are inserted in the IMPC-Burnup2.0.In order to verify IMPC-Burnup2.0,burnup calculation in cell,assembly and core scales are verified based on MOX cell,VVER-1000 LEU assembly and OECD fast reactor benchmark problem respectively.For ADS burnup application,the IAEA-ADS and OECD/NEA MA benchmark are verified,parameters such as keff and nuclide contents are basically consistent with reference results from other institutions.Therefore,this program can be used for ADS burnup analysis.Finally,in order to further improve particle transport capacity in the code system,INCL++5.1 intranuclear cascade model and ABLA evaporation de-excitation model are embedded into the open source Monte Carlo code Open MC to develop an internal proton-neutron coupled transport IMPC-MC1.0.This code can complete the proton spallation reaction,high energy neutron transport and secondary particles transport process.Based on the BNL-AGS experimental benchmark,proton spallation reaction simulation for different target materials and 800 MW lead-bismuth cooled ADS target-reactor design of JAEA,reliability of IMPC-MC1.0 is verified.