4–8 Jun 2017
Marriott Shanghai City Center
Asia/Shanghai timezone

Development and application of advanced nuclear software SuperMC for fusion

7 Jun 2017, 10:40
20m
Salon 3

Salon 3

Oral Neutronics and multiphysics simulation W.OA3: Neutronics and Multiphysics Analysis

Speaker

Dr Jing Song (Institute of Nuclear Energy Safety Technology, CAS · FDS Team)

Description

Jing Song*, Liqin Hu, Pengcheng Long, Lijuan Hao, Mengyun Cheng, Huaqing Zheng, Shengpeng Yu, Guangyao Sun, Qi Yang, Bin Wu, Chaobin Chen, Peng He, Peng Ge,
Yican Wu, FDS Team

Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences
No. 350 Shushanhu Road, Hefei, Anhui, 230031, China

jing.song@fds.org.cn


SuperMC, developed by FDS Team in China, is a general, intelligent, accurate and precise program for the nuclear design and safety analysis. The latest version supports n, γ transport calculation, depletion calculation, activation calculation and shutdown dose rate(SDR) calculation, with the advanced features of automatic modeling, visualization and cloud computing.

Built-in activation calculation was newly developed based on a new matrix exponential method-Chebyshev rational approximation method (CRAM) method. Depth first searching based dynamic construction of activation chain was developed to avoid redundant nuclides. Adaptive reduction of massive matrix order was developed to accelerate coefficient matrix solving. The SDR calculation was developed based on both regorous two step (R2S) method and direct one step(D1S) method.

To improve performance of transport calculation, several novel methods were developed. Global Weight Window Generator (GWWG) was proposed, in which the expected contribution to a uniform particle distribution was considered, and an automatic iteration scheme was implemented to speed up the weight window generation.

Hybrid geometry representation and modeling methods was implemented in SuperMC. Hybrid facet and constructive geometry modeling method has been implemented, which enables SuperMC directly using complicate CAD models including spline surfaces without pre-processing. Besides, unstructured mesh was newly applied in SuperMC to enhance the description capability of arbitrary shape and process the multi-physics coupling analysis. A new speedup method called feature size tree was presented to accelerate the unstructured mesh geometry processing and further reduce the memory consumption.

SuperMC has been verified and validated by more than 2000 benchmark models and experiments, such as SINBAD, ITER C-lite. Meanwhile, series of SDR benchmark tests were used to verfiy the activation and SDR calculation, such as the ITER shutdown dose rate benchmark and ITER-T426 shutdown dose rate experiment. The resluts of SuperMC agree well with other codes and experiment results. In addition, with the new developed acceleration methods, calculation speed of SuperMC was greatly increased by about 200 times for ITER Alite model.

Eligible for student paper award? No

Authors

Dr Jing Song (Institute of Nuclear Energy Safety Technology, CAS · FDS Team) Prof. Liqin Hu (Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences) Dr Pengcheng Long (Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences) Dr Lijuan Hao (Institute of Nuclear Energy Safety Technology, CAS · FDS Team) Dr Mengyun Cheng (Institute of Nuclear Energy Safety Technology, CAS · FDS Team) Dr Shengpeng Yu (Institute of Nuclear Energy Safety Technology, CAS · FDS Team) Dr Guangyao Sun (Institute of Nuclear Energy Safety Technology, CAS · FDS Team) Dr Qi Yang (Institute of Nuclear Energy Safety Technology, CAS · FDS Team) Prof. Yican Wu (Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences) Dr Bin Wu (Institute of Nuclear Energy Safety Technology, CAS · FDS Team) Dr Peng He (Institute of Nuclear Energy Safety Technology, CAS · FDS Team) Dr Huaqing Zheng (Institute of Nuclear Energy Safety Technology, CAS · FDS Team)

Presentation materials

There are no materials yet.