Development of a New Monte Carlo reactor physics code

摘要: Monte Carlo neutron transport codes are widely used in various reactor physics applications, traditionally related to criticality safety analyses, radiation shielding problems, detector modelling and validation of deterministic codes. The main advantage the method is capability model geometry interaction without major approximations. disadvantage that complicated systems very computing-intensive, which restricts applications some extent. importance calculation likely increase future, along with development computer capacities parallel calculation. An interesting near-future application for generation input parameters simulator These coupled LWR full-core analyses typically based on fewgroup nodal diffusion methods. data consists homogenised constants, presently generated using lattice task becoming increasingly challenging, nuclear technology. Calculations involving high-burnup fuels, advanced MOX technology next-generation cause problems if code cannot keep up applications. A potential solution use codes, brings all advantages method.