The development of advanced reactor designs imposes higher demands on neutronic numerical methods.To achieve accurate and efficient simulation of complex problems,this paper introduces a hybrid discontinuous Galerkin(HDG)method based on the first-order hyperbolic neutron transport equation(NTE).The method decouples the original equation into independent equations for each angular direction using the discrete-ordinates(SN)method in angular space.In spatial discretization,this paper employs an upwind scheme that results in a blocked-lower-triangular global matrix coupling system,making it well-suited for complex,geometrically heterogeneous neutron transport scenarios with a large number of meshes.The study evaluates the performance of the proposed HDG method using the TAKEDA1 benchmark and a heterogeneous assembly problem.The results demonstrate that the HDG method achieves stable convergence for the aforementioned problems,with a maximum error between the effective multiplication coefficient keff and the reference solution of 108 pcm(1pcm=10-5).In addition,compared with the traditional second-order even-parity method,the first-order HDG method is more efficient in spatial scanning,and the acceleration ratio is about 2 times in the above examples.Therefore,the proposed HDG method can provide an alternative solution for complex reactor problems.
Hybrid discontinuous Galerkin(HDG)Neutron transport equation(NTE)Upwind schemeDiscrete-ordinates(SN)
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