Abstract Efforts to develop high-fidelity, in silico or ab initio, high performance multi-physics tools are undertaken by many groups due to the availability of relatively cheap, large-scale parallel computers. To this end, an internal coupling between the Monte Carlo reactor physics code Serpent 2 and the sub-channel code SUBCHANFLOW has been developed. The coupled code system is intended to serve as reference for deterministic reactor dynamics code developments in the future. It exploits the fact that Serpent was conceived as a lattice code for such deterministic tools. The coupling utilizes Serpent's recently introduced universal multi-physics interface. With the multi-physics interface enabled, Serpent treats temperature dependence of nuclear data using the target motion sampling method. Since the target motion sampling methodology cannot be applied to thermal bound-atom scattering or unresolved resonances, a stochastic mixing fall back algorithm to enable the simulation of thermal reactors has been implemented. The developed coupled code is verified by code-to-code comparison with an external coupling of the Monte Carlo tool TRIPOLI4 and SUBCHANFLOW as well as the internally coupled code MCNP5/SUBCHANFLOW. Simulation results of all code systems were found to be in good agreement. Thereafter, the second exercise of the OECD/NEA and U.S. NRC PWR MOX/UO2 core transient benchmark is studied to demonstrate that Serpent 2/SUBCHANFLOW may be employed to analyze realistic, industry-like cases such as a full PWR core under hot full power conditions in a reasonable amount of time. The obtained simulation results are compared to known benchmark solutions and the numerical performance of Serpent 2/SUBCHANFLOW is analyzed to assess the feasibility of routine application. While Serpent 2/SUBCHANFLOW's performance in terms of physics and numerical efficiency is found to be generally satisfactory, options to further improve the coupled tool concerning both aspects are discussed. Afterwards, first efforts to validate Serpent 2/SUBCHANFLOW using the hot zero power state of the cycle 1 of the BEAVRS benchmark are presented.
ASJC Scopus subject areas
- Nuclear Energy and Engineering