Abstract
The increasing use of Monte Carlo methods for core analysis is fostered by the huge and cheap computer power available nowadays e.g. in large HPC. Apart from the classical criticality calculations, the application of Monte Carlo methods for depletion analysis and cross section generation for diffusion and transport core simulators is also expanding. In addition, the development of multi-physics codes by coupling Monte Carlo solvers with thermal hydraulic codes (CFD, subchannel and system thermal hydraulics) to perform full core static core analysis at fuel assembly or pin level has progressed in the last decades. Finally, the extensions of the Monte Carlo codes to describe the behavior of prompt and delay neutrons, control rod movements, etc. has been started some years ago. Recent coupling of dynamic versions of Monte Carlo codes with subchannel codes make possible the analysis of transient e.g. rod ejection accidents and it paves the way for the simulation of any kind of design basis accidents as an alternative option to the use of diffusion and transport based deterministic solvers. The H2020 McSAFE Project is focused on the improvement of methods for depletion considering thermal hydraulic feedbacks, extension of the coupled neutronic/thermal hydraulic codes by the incorporation of a fuel performance solver, the development of dynamic Monte Carlo codes and the development of methods to handle large depletion problems and to reduce the statistical uncertainty. The validation of the multi-physics tools developed within McSAFE will be performed using plant data and unique tests e.g. the SPERT III E REA test. This paper will describe the main developments, solution approaches, and selected results.
Highlights
Fast running and highly accurate numerical methods and codes able to predict local safety parameters of reactor cores at steady state conditions, e.g. during the operation lifetime (BOC, EOC) or under transient situations, are urgently needed by manufacturers, utilities and regulators to optimize core designs and to assess the safety features [1]
The development of multi-physics codes by coupling Monte Carlo solvers with thermal hydraulic codes (CFD, subchannel and system thermal hydraulics) to perform full core static core analysis at fuel assembly or pin level has progressed in the last decades
The H2020 McSAFE Project is focused on the improvement of methods for depletion considering thermal hydraulic feedbacks, extension of the coupled neutronic/thermal hydraulic codes by the incorporation of a fuel performance solver, the development of dynamic Monte Carlo codes and the development of methods to handle large depletion problems and to reduce the statistical uncertainty
Summary
Fast running and highly accurate numerical methods and codes able to predict local safety parameters of reactor cores at steady state conditions, e.g. during the operation lifetime (BOC, EOC) or under transient situations, are urgently needed by manufacturers, utilities and regulators to optimize core designs and to assess the safety features [1]. Efforts are underway worldwide to develop multi-physics tools based on Monte Carlo codes which are intended to have the capability of performing time-dependent solutions considering the behavior of prompt and delayed neutrons These tools will be able to treat safety related transients and time dependent geometry changes such as control rods movement. McSAFE gathers experts on code development (neutronic, thermal hydraulic and thermo-mechanics) and multi-physics coupling from universities, research centers, and industry with a total of twelve partners from nine European countries Under this framework, different Monte Carlo codes e.g. TRIPOLI [4], SERPENT [5], MONK [6] and MCNP [7], subchannel codes such as SCF (SubChanFlow) [8] and the fuel performance code TRANSURANUS [9] are being improved and optimized for high fidelity simulations.
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