Neutronics calculation model plays a very important role in applying a specify simulation of a reactor system. The accuracy of the reactor core neutronics calculation results can hugely affect the final results of the reactor system analysis. At present, most of the system analysis codes apply the point reactor kinetics calculation model as the method to do the neutronics calculation. In normal conditions, the point kinetics model can get a satisfying result. But in large scale reactor core or in several accident conditions in which the reactor core power distribution varies greatly in space, the point kinetics model may have a result with a large error caused by ignoring the space effect. To solve this problem, a system code with a 3D neutronics calculation model inside is required. SAC is a system analysis code with different versions which is developed by North China Electric Power University. In the SAC-3D version, we apply the hexagonal nodal expansion method for the diffusion equation to conduct the core flux (power) distribution calculation. Furthermore, we developed a new version of SAC with a 3D neutronics calculation model by applying the transport theory in hexagonal geometry. In this paper we validate both of these two versions of SAC series codes with EBR-II SHRT-45R neutronics benchmark problem. The results we got were also been compared with the other project participants’ results.


Code to Code Validation of SAC-3D Based on EBR-II Benchmark Problem

Division / Sponsors: 
Power Division & Nuclear Engineering Division (NED)

Power Conference
Paper Proceedings: https://asmedigitalcollection.asme.org/POWER/POWER2020/volume/83747

International Conference on Nuclear Engineering
Paper Proceedings: https://asmedigitalcollection.asme.org/ICONE/ICONE2020/volume/83761

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