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, et...
The theoretical aspects behind the reactor depletion capability of the Monte Carlo code MCS develope...
International audiencePredictive modelling capabilities have long represented one of the pillars of ...
This paper presents the verification and validation elements of the UNIST in-house Monte Carlo code,...
The increasing use of Monte Carlo methods for core analysis is fostered by the huge and cheap comput...
The increasing use of Monte Carlo methods for core analysis is fostered by the huge and cheap comput...
A whole-core depletion analysis of OPR-1000 using MCS coupled with FRAPCON is presented in this pape...
The Monte Carlo code MCS is developed at Ulsan National Institute of Science and Technology for the ...
MCS is an in-house Monte Carlo neutron transport code under development at Ulsan National Institute ...
A new Monte Carlo (MC) neutron/photon transport code, called MCS, has been developed at Ulsan Nation...
To simulate reactor transients for safety analysis with the Monte Carlo method the generation and de...
Safety analysis of innovative reactor designs requires three dimensional modeling to ensure a suffic...
A refueling capability has been implemented in the Monte Carlo code MCS under development at the Uls...
International audiencePredictive modelling capabilities have long represented one of the pillars of ...
This paper presents the preliminary solutions of BEAVRS cycle 1 depletion by Monte Carlo (MC) code M...
This paper presents a whole-core depletion analysis of Yonggwang Unit 3, cycles 1 and 2, by using MC...
The theoretical aspects behind the reactor depletion capability of the Monte Carlo code MCS develope...
International audiencePredictive modelling capabilities have long represented one of the pillars of ...
This paper presents the verification and validation elements of the UNIST in-house Monte Carlo code,...
The increasing use of Monte Carlo methods for core analysis is fostered by the huge and cheap comput...
The increasing use of Monte Carlo methods for core analysis is fostered by the huge and cheap comput...
A whole-core depletion analysis of OPR-1000 using MCS coupled with FRAPCON is presented in this pape...
The Monte Carlo code MCS is developed at Ulsan National Institute of Science and Technology for the ...
MCS is an in-house Monte Carlo neutron transport code under development at Ulsan National Institute ...
A new Monte Carlo (MC) neutron/photon transport code, called MCS, has been developed at Ulsan Nation...
To simulate reactor transients for safety analysis with the Monte Carlo method the generation and de...
Safety analysis of innovative reactor designs requires three dimensional modeling to ensure a suffic...
A refueling capability has been implemented in the Monte Carlo code MCS under development at the Uls...
International audiencePredictive modelling capabilities have long represented one of the pillars of ...
This paper presents the preliminary solutions of BEAVRS cycle 1 depletion by Monte Carlo (MC) code M...
This paper presents a whole-core depletion analysis of Yonggwang Unit 3, cycles 1 and 2, by using MC...
The theoretical aspects behind the reactor depletion capability of the Monte Carlo code MCS develope...
International audiencePredictive modelling capabilities have long represented one of the pillars of ...
This paper presents the verification and validation elements of the UNIST in-house Monte Carlo code,...