Progress and Applications of MCAM: Monte Carlo Automatic Modeling Program for Particle Transport Simulation

Wang, Guozhong; Xiong, Jian; Peng, Long; Wang, DianXi; Zhao, Kai; Zeng, Qin; Hu, Liqin; Ying, Dongchuan; Sagara, A.; Tanaka, Teruya; Muroga, T.

doi:10.15669/pnst.2.821

Cited by 8 publications

(3 citation statements)

References 11 publications

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“…Conversely, inversion from the calculation model to the CAD model for visualization to locate the defects and errors and further updates which will accelerate the redesign process is also introduced to SuperMC. It works by sequentially parsing the calculation model, constructing the CSG tree, making primitive solids and building real solids from the bottom to the top of the CSG tree (Wu and FDS Team, 2009;Wang et al, 2011).…”

Section: Multi-physics Coupling Calculation Methodsmentioning

confidence: 99%

CAD-based Monte Carlo program for integrated simulation of nuclear system SuperMC

Song

Zheng

et al. 2015

Annals of Nuclear Energy

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337

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a b s t r a c tMonte Carlo (MC) method has distinct advantages to simulate complicated nuclear systems and is envisioned as a routine method for nuclear design and analysis in the future. High-fidelity simulation with MC method coupled with multi-physics phenomena simulation has significant impact on safety, economy and sustainability of nuclear systems. However, great challenges to current MC methods and codes prevent its application in real engineering projects. SuperMC, developed by the FDS Team in China, is a CAD-based Monte Carlo program for integrated simulation of nuclear systems by making use of hybrid MC and deterministic methods and advanced computer technologies. The design objective, architecture and main methodology of SuperMC are presented in this paper. SuperMC2.1, the latest version, can perform neutron, photon and coupled neutron and photon transport calculation, geometry and physics modeling, results and process visualization. It has been developed and verified by using a series of benchmarking cases such as the fusion reactor ITER model and the fast reactor BN-600 model. SuperMC is still in its evolution process toward a general and routine tool for the simulation of nuclear systems.

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Section: Multi-physics Coupling Calculation Methodsmentioning

confidence: 99%

CAD-based Monte Carlo program for integrated simulation of nuclear system SuperMC

Song

Zheng

et al. 2015

Annals of Nuclear Energy

Self Cite

337

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“…MCAM has already been applied to many complex nuclear facilities successfully, including the International Thermonuclear Experimental Reactor (ITER) [19], the super-conducting tokamak EAST [20] being operated in China, the FDS series reactors design [21] and Compact Reversed Shear Tokamak Reactor (CREST) [22], etc.…”

Section: Introduction To Mcammentioning

confidence: 99%

Preliminary study on CAD-based method of characteristics for neutron transport calculation

Chen¹,

Zheng²,

Sun³

et al. 2014

Chinese Phys. C

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Abstract:The method of characteristics (MOC) is widely used for neutron transport calculation in recent decades. However, the key problem determining whether MOC can be applied in highly heterogeneous geometry is how to combine an effective geometry modeling method with it. Most of the existing MOC codes conventionally describe the geometry model just by lines and arcs with extensive input data. Thus they have difficulty in geometry modeling and ray tracing for complicated geometries.In this study, a new method making use of a CAD-based automatic modeling tool MCAM which is a CAD/Image-based Automatic Modeling Program for Neutronics and Radiation Transport developed by FDS Team in China was introduced for geometry modeling and ray tracing of particle transport to remove those limitations. The diamond-difference scheme was applied to MOC to reduce the spatial discretization errors of the flat flux approximation. Based on MCAM and MOC, a new MOC code was developed and integrated into SuperMC system, which is a Super Multi-function Computational system for neutronics and radiation simulation. The numerical results demonstrated the feasibility and effectiveness of the new method for neutron transport calculation in MOC.

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“…MCAM also supports some supplementary functions such as creation and repair of CAD models and analysis of physics properties. MCAM has been widely used in the neutronics modeling of many nuclear devices [9][10][11][12][13][14][15][16][17].…”

Section: Introductionmentioning

confidence: 99%

Use of MCAM in creating 3D neutronics model for ITER building

Zeng

Wang

Dang

et al. 2012

Fusion Engineering and Design

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Progress and Applications of MCAM: Monte Carlo Automatic Modeling Program for Particle Transport Simulation

Cited by 8 publications

References 11 publications

CAD-based Monte Carlo program for integrated simulation of nuclear system SuperMC

CAD-based Monte Carlo program for integrated simulation of nuclear system SuperMC

Preliminary study on CAD-based method of characteristics for neutron transport calculation

Use of MCAM in creating 3D neutronics model for ITER building

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