【摘 要】
：
Great challenges exist in the current Monte Carlo(MC)methods in nuclear design and analysis of advanced nuclear energy systems.Super MC is a general,intelligent,accurate and precise simulation softwar
【机 构】
：
Key Laboratory of Neutronics and Radiation Safety,Institute of Nuclear Energy Safety Technology,Chin
【出 处】
：
第13届中日双边先进能源系统和聚变裂变工程材料会议(CIS-13)
论文部分内容阅读
Great challenges exist in the current Monte Carlo(MC)methods in nuclear design and analysis of advanced nuclear energy systems.Super MC is a general,intelligent,accurate and precise simulation software system for the nuclear design and safety evaluation.It is designed to perform the comprehensive neutronics calculation,taking the radiation transport as the core and including the depletion,radiation source term/dose/biohazard,material activation and transmutation,etc.The latest version of Super MC can accomplish the transport calculation of n,γ and depletion calculation of isotopes.It is integrated with the functions of automatic modeling,visualization and cloud computing.
其他文献
As a study of the mechanism of hydrogen absorption into promising hydrogen storage materials,two ZrNiAl type uranium intermetallic compounds,UNiAl and UPtAl,were investigated with the ab initio calcul
Due to the good radiation resistance and low activation performance,the reduced activation ferritic/martensitic(RAFM)steel has been selected as the primary candidate structural material for the fusion
Irradiation-induced hardening and premature fracture are major concerns for the intermediate-temperature application of high Cr ferritic/martensitic steels as structural materials in nuclear reactors
The combination of irradiation tolerance,high strength,and thermal stability is a key requirement for structural materials used in nuclear reactor cores.It is challenging to develop bulk materials pos
The feasibility and benefits of applying grain boundary engineering(GBE)to the fuel cladding material 15-15Ti austenitic stainless steels of liquid-metal-cooled-fast-reactor for reducing the void swel
Some developments on neutron measurement techniques are required to meet diagnostic challenges,including very high levels of neutron and gamma fluxes,nuclear heating,and harsh environmental conditions
Fusion-fission hybrid reactor is a solution to overcome difficulties of fission energy development with the features of energy production,fuel breeding and waste transmutation.It is a more feasible ap
The effects of grain boundary characters on the morphology evolution of grain boundary carbides in Inconel Alloy 600 and 690 with high proportional low Σ coincidence site lattice(CSL)boundaries aged a
The Monte Carlo method is becoming widely used to do the transport calculation in the reactor physics because of its advantages of dealing with continue energy cross sections and arbitrary geometry.A
The main task for High Flux Engineering Test Reactor(HFETR)is to carry out the irradiation test of nuclear materials,which successfully calls for providing the materials neutron flux within the irradi