Shielding calculation based on SINBAD fusion benchmarks using cosRMC

Abstract

BackgroundFusion reactors have the characteristics of high neutron energy, large spatial scales, complex geometric structures, and large radiation attenuation gradients, which make nuclear design and analysis more challenging.PurposeThis study aims to verify the accuracy of the calculation of Monte Carlo code cosRMC on the material shielding effect in fusion reactor applications.MethodsTwo deep penetration benchmarks, i.e., FNS-Duct (Fusion Neutron Source Dogleg Duct Streaming) and FNS-W (FNS Clean Experiment on Tungsten Cylindrical Assembly) from the Shielding Integral Benchmark Archive Database (SINBAD), were taken for simulation study of the penetration behaviors of neutrons in models under different geometric shapes and materials. First of all, detailed cosRMC models was established based on benchmark experimental models, neutron flux spectra of detectors at different penetration depths in benchmark experiments were calculated using cosRMC. Then, the variance reduction technique of cell importance was applied to improving the accuracy of cosRMC in calculating deep penetration problems. Finally, neutron flux spectra calculated by cosRMC were compared with those calculated by MCNP5, as well as the experimental results of the benchmarks.ResultsThe comparison results show that the calculations of cosRMC conform to that of MCNP5 with relative deviations of less than three times the standard errors. Both calculation results match well with the experimental values.ConclusionsThe study verifies that cosRMC can be applied to shielding calculations of fusion reactors.

Keywords

• fusion benchmark
• shielding calculation
• sinbad
• cosrmc