Research On Reconstruction And Linearization Of Resonance Cross Section And Fabrication Method Of Ultrafine Energy Group Cross Section Of Fast Reactor

The International Forum for Generation IV Reactors selected six candidates for Generation Ⅳ reactor types,among which fast reactor is one of the main types.As an advanced nuclear energy system,fast reactor design has high requirements for safety and economy.Fast reactor core physical calculation is the foundation of fast reactor design,and the results provide the key core physical parameters for fast reactor design.The cross section data of core material related nuclides is the basic input parameter of fast reactor core physical calculation,and is the main factor that directly affects the calculation accuracy of core key physical quantities.Therefore,improving the accuracy of cross section data for fast reactor is the key to guarantee the accuracy of physical calculation results for fast reactor.In this paper,based on the IRPS laboratory of North China Electric Power University,two different fast reactor cross section fabrication technology routes,reconstruction of the resonance cross section research and fast reactor ultra-fine energy group cross section fabrication method research were carried out respectively.First of all,based on the traditional resonance cross section reconstruction and linearization method,developed resonance cross section reconstruction code ReconXS,and based on ENDF/B-VII.1 evaluation nuclear library ReconXS are verified,in the numerical verification of single nuclide cross section,the accuracy of ReconXS processing results for typical nuclides is similar to that of NJOY’s RECONR module.A series of calculation results of critical benchmark examples show that the deviation of the cross section calculation based on the two treatments is within 50pcm,which is in good agreement.Secondly,based on the evaluation kernel database ENDF/B-Ⅶ.1 and ENDF/B-VIII.0,Knight2.0-V7.1 and Knight2.0-V8.0 are respectively made,and a series of critical benchmark questions are selected to calculate and verify them respectively.The average error between the two calculation results and the MCNP calculation results is 98pcm and 88.5 pcm,respectively,which is in good agreement.The calculated results of statistical parameters χ2 show that Knight2.0-V8.0 database has better stability.Finally,based on the fast reactor multi-group cross section processing code MGGC,two methods for calculating the wide group cross section generated by neutron energy spectrum in each material region of fast reactor core are developed.The fast reactor benchmark example ZPPR-9 is calculated by using MGGC and Knight2.0-V8.0 database to verify the two different wide group cross section generation methods.The results show that the two methods to produce wide group of cross section And results of deviation of hyperfine can 62 pcm and 9 pcm respectively,and the deviation between the calculated results of two methods is only 53 pcm,also good agreement,In addition,the energy spectra of the two are in good agreement,only in the non-fission zone(such as the reflector)there will be a little error,in line with the expected accuracy requirements..In addition,BN-600,a fast reactor benchmark,is selected to calculate the core physical parameters,so as to further verify the applicability of the cross-section generation technology route in complex reactors.In the calculation results,most of the physical parameters are in good agreement with the reference value,and only the deviation of the physical parameters related to 56Fe is found to be slightly larger.In the preliminary analysis,the reason for the slightly larger relative deviation is related to the processing method of narrow resonance approximation,and further improvement can be made in this aspect in the future.In summary,the resonance reconstruction results of the typical nuclides by ReconXS are comparable to the accuracy of the reference NJOY,and can be used as the basic module of the advanced nuclear cross section processing code AXSP.The processing results are reliable and can be used for subsequent cross section processing.The results verified by Knight2.0 are in good agreement with the reference results,which can be used for core physics calculation of fast reactors.The wide group cross sections generated by the two methods are verified to meet the expected accuracy requirements,and the wide group cross sections generated by the two methods can be used in fast reactor core physical calculation.