It is important for nuclear reactor physics calculation to generate accurate multigroup cross section libraries by using evaluation nuclear data libraries. A new evaluated nuclear data library processing code, named as AXSP (Advanced Cross Section Processing Code) was developed with independent intellectual property rights. The GroupXS module was developed with the ability of generating multi-group cross-sections based on the Bondarenko method which is always a favorable approximation for the fast spectrum reactor, and the method was also used in GROUPR of NJOY. To verify the accuracy of the GroupXS module, the GROUPR module of NJOY was used, and we corrected three numerical verification bugs of GROUPR. The bugs were described in this study. By comparing the calculation results with GROUPR of NJOY2016, the relative error of multigroup flux, multigroup cross sections of various reaction types are less than 0.01%, and the relative errors of transfer matrices of various reaction types are basically less than 0.1%. All the neutron reaction types of all nuclides in ENDF/B-VII.1, ENDF/B-VIII.0 and CENDL-3.2 can be processed by GroupXS, and the multigroup cross sections generated by GroupXS of AXSP have a good agreement with that generated by GROUPR of NJOY2016.
In order to improve the accuracy of fast reactor physical analysis, two libraries with 1968-group neutron and 21-group photon were generated based on ENDF/B-VIII.0 and ENDF/B-VII.1 data by using NJOY2016. A code, named TXMAT2.0, was developed to process the two libraries to generate ultrafine group neutron and photon cross sections and Kinetic Energy Release in Material (KERMA) factors. To perform the verification of the two libraries, ICSBEP benchmarks for critical verification, and the sample 1D benchmark were selected. Several results were in good agreement with reference data. For the RBEC-M benchmark, the power distribution based on the ultrafine group library was good.
To meet the needs of fast reactor high precision nuclear data processing, a high precision multi-group cross section processing program MAGIC based on continuous point cross section is developed, which can provide accurate multi-group cross section for fast reactor deterministic program. The MAGIC program uses 1/120 lethargy width to divide the energy interval, and a total of 2082 energy groups are divided in 0.414eV∼14.2MeV for fast reactor energy region. The main functions of the program are as follows: (1) by using the problem dependent neutron spectrum, the effect of resonance interference can be well considered. (2) The resonance self-shielding factor iteration method can be used to better consider the interaction of the resonance self-shielding in the resolved and unresolved resonance energy regions of multiple nuclides. (3) When calculating the elastic scattering matrix, the resonance phenomenon is considered in the one-dimensional elastic scattering cross section, and the prefabricated scattering transfer probability table can greatly improve the calculation efficiency of the scattering matrix under the ultra-fine group energy framework on the premise of maintaining the accuracy. In terms of benchmark verification, the effective increment coefficient was verified by fast energy spectrum critical benchmark based on the multi-group cross section generated by MAGIC. The difference between the calculated results and those of the Monte Carlo program and NJOY was small, which preliminatively verified the effectiveness of the multi-group cross section generated by MAGIC program in the calculation of deterministic method.
The advanced reactor design needs an accurate cross-section generation code. In this study, a new nuclear data processing code AXSP is developed, and the method and performance of which are described. Compared with the NJOY program, the precision of the unresolved resonance processing module UnresXS has been significantly improved due to the adoption of a more accurate solution method and the consideration of in-sequence overlap integrals. The time consumption of PUnresXS has been decreased significantly due to an optimized sorting algorithm. At the same time, other modules of AXSP are relatively comprehensive. The function of resolved resonance cross-section reconstruction and linearization is the ReconXS module. The Doppler broadening module is BroadXS by using Gauss–Hermite quadrature and Gauss–Legendre quadrature from 0 K temperature pointwise cross section to any temperature which is defined by the user. The shielding factor in the unresolved resonance energy region is calculated by the UnresXS or the PUnresXS module, which are developed based on the Bondarenko method and the probability table method, respectively. The ACE formatted cross sections for the Monte Carlo code is processed by the ACEXS module, and the multigroup cross sections are generated by the GroupXS module. The cross sections processed by different modules were verified by the NJOY2016 code, and the multigroup cross sections were also verified by using the critical benchmarks. The multiplication factor difference between AXSP and NJOY2016 is less than 20 pcm. In addition to this, the ZPR6/7 fast reactor is used for ACE format library verification. The results show that the criticality calculated by AXSP has a good agreement with that of NJOY2016.
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