LAUSR

Abstract As wrapping tools for coupling Monte Carlo (MC) neutron transport code with depletion solver, four different coupling schemes are implemented in Reactor Monte Carlo Code (RMC) developed at Tsinghua University, and verified in two assembly testing cases derived from VERA international benchmark. In this paper, accuracy and time consumption are comparatively analyzed, as well as memory requirement which is significant in large-scale burnup calculation. Results illustrate that beginning of step approximation, as the basic and simplest coupling method, performed with relatively poor accuracy. With nearly the same efficiency, two predictor-corrector methods provide identical accuracy better than the beginning of step approximation, but require different computer memories. High order predictor-corrector combined with sub-step method (HSPC) has the best performance and requires the most memory. By means of hybrid parallelism, domain decomposition and parallel depletion solver in RMC, HSPC is able to be applied in large-scale burnup problem.