Speaker
Jing Song
(Institute of Nuclear Energy Safety Technology)
Description
Great challenges exist in real fusion engineering projects for the current Monte Carlo (MC) methods including the calculation modeling of complex geometries, simulation of deep penetration problem, slow convergence of complex calculation, lack of experimental validation for new physical features, etc.
Several novel and advanced capabilities of the latest version of MC program SuperMC for fusion applications were introduced in this paper. An automatic and intelligent CAD-based modeling function is developed. The latest ITER reference model C-Lite with complex solids and hierarchy structure can be modeled. The output data can be automatically and intelligently visualized by mixing with the input models according to users’ interests. The simulation process and real-time dose can be visualized to test and evaluate the operational or maintenance tasks and assist the supervisors to plan better working activities. Three dimensional domain hybrid MC and discrete ordinates (SN) modeling and transport calculation method with transition region has been developed. Adaptive variance reduction technique for local tally with hybrid MC–deterministic method with weight window smoothing was studied. The optimal spatial subdivision method was employed to enhance the geometry navigation performance. The bounding box algorithm can be specifically customized and applied to accelerate the basic function of calculating the distance to volume boundary. Based on Chebyshev rational approximation method, the activation calculation function was developed. Cloud computing framework makes the calculation and analysis more attractive as a service.
SuperMC has been verified and validated by more than 2000 benchmark models and experiments. Series of fusion reactors were employed to validate the comprehensive capability. As the supplementary of validation experiments for fusion applications, an experiment to validate the deep penetration problem of radiation shielding using High Intensity D-T Fusion Neutron Generator (HINEG) which produce 14.1MeV neutrons with ~101212n/s beam yield is being particularly conducted.
Co-authors
Bin Wu
(Institute of Nuclear Energy Safety Technology,Chinese Academy Sciences, Hefei, Anhui, China)
Chaobin Chen
(Institute of Nuclear Energy Safety Technology,Chinese Academy Sciences, Hefei, Anhui, China)
Guangyao Sun
(Institute of Nuclear Energy Safety Technology,Chinese Academy Sciences, Hefei, Anhui, China)
Huaqing Zheng
(Institute of Nuclear Energy Safety Technology,Chinese Academy Sciences, Hefei, Anhui, China)
Jing Song
(Institute of Nuclear Energy Safety Technology,Chinese Academy Sciences, Hefei, Anhui, China)
Lijuan Hao
(Institute of Nuclear Energy Safety Technology,Chinese Academy Sciences, Hefei, Anhui, China)
Ling Fang
(Institute of Nuclear Energy Safety Technology,Chinese Academy Sciences, Hefei, Anhui, China)
Liqin Hu
(Institute of Nuclear Energy Safety Technology,Chinese Academy Sciences, Hefei, Anhui, China)
Mengyun Cheng
(Institute of Nuclear Energy Safety Technology,Chinese Academy Sciences, Hefei, Anhui, China)
Peng He
(Institute of Nuclear Energy Safety Technology,Chinese Academy Sciences, Hefei, Anhui, China)
Pengcheng Long
(Institute of Nuclear Energy Safety Technology,Chinese Academy Sciences, Hefei, Anhui, China)
Qi Yang
(Institute of Nuclear Energy Safety Technology,Chinese Academy Sciences, Hefei, Anhui, China)
Shengpeng Yu
(Institute of Nuclear Energy Safety Technology,Chinese Academy Sciences, Hefei, Anhui, China)
Tao He
(Institute of Nuclear Energy Safety Technology,Chinese Academy Sciences, Hefei, Anhui, China)
Tongqiang Dang
(Institute of Nuclear Energy Safety Technology,Chinese Academy Sciences, Hefei, Anhui, China)
Yican Wu
(Institute of Nuclear Energy Safety Technology,Chinese Academy Sciences, Hefei, Anhui, China)
