This paper describes the recent developments in the multi-physics capabilities of the Serpent Monte Carlo code concerning coupled multi-physics calculations with fuel behavior feedback. We cover the structure and operation of the fuel behavior interface in Serpent 2 as well as the coupled calculation routines implemented for steady state multi-physics calculations with any internally or externally coupled solver. The intended solution flow and code-to-code communication in internally and externally coupled multi-physics simulations is described alongside with the stochastic approximation based solution relaxation methods implemented in Serpent. The two-level multi-physics coupling scheme in Serpent 2 is demonstrated by obtaining a coupled s...
Nowadays, different multi-physics approaches are available, in order to improve the reactor safety a...
In nuclear reactor analysis, a relevant challenge is to achieve a suitable global description of nuc...
In coupled calculations with Monte Carlo neutronics and thermal hydraulics the Monte Carlo code is u...
This paper describes the recent developments in the multi-physics capabilities of the Serpent Monte ...
The main goal of this work was to couple the Monte Carlo neutronics code Serpent~2 with a CFD solver...
The increasing interest in high fidelity modeling of power and test reactors drives the development ...
This paper describes the built-in calculation routines in the reactor physics code Serpent 2 that pr...
This paper describes the unique way of simultaneously solving the power and temperature distribution...
In nuclear reactor analysis, a relevant challenge is to achieve a suitable global description of nuc...
The accurate modeling of nuclear reactors is essential to the safe and economic operation of current...
A new method of Serpent–OpenFOAM coupling is developed as a multi-physics model for Advanced Lead Fa...
The main goal of this work was to couple the Monte Carlo neutronics code Serpent 2 with a CFD solver...
In this work coupled problems with neutronics and thermal-hydraulics are solved with Serpent 2 Monte...
In nuclear reactors, fuel burnup calculations assess the time evolution of both the fuel composition...
Released in 2009, the Serpent Monte Carlo code has established itself as a highly efficient and powe...
Nowadays, different multi-physics approaches are available, in order to improve the reactor safety a...
In nuclear reactor analysis, a relevant challenge is to achieve a suitable global description of nuc...
In coupled calculations with Monte Carlo neutronics and thermal hydraulics the Monte Carlo code is u...
This paper describes the recent developments in the multi-physics capabilities of the Serpent Monte ...
The main goal of this work was to couple the Monte Carlo neutronics code Serpent~2 with a CFD solver...
The increasing interest in high fidelity modeling of power and test reactors drives the development ...
This paper describes the built-in calculation routines in the reactor physics code Serpent 2 that pr...
This paper describes the unique way of simultaneously solving the power and temperature distribution...
In nuclear reactor analysis, a relevant challenge is to achieve a suitable global description of nuc...
The accurate modeling of nuclear reactors is essential to the safe and economic operation of current...
A new method of Serpent–OpenFOAM coupling is developed as a multi-physics model for Advanced Lead Fa...
The main goal of this work was to couple the Monte Carlo neutronics code Serpent 2 with a CFD solver...
In this work coupled problems with neutronics and thermal-hydraulics are solved with Serpent 2 Monte...
In nuclear reactors, fuel burnup calculations assess the time evolution of both the fuel composition...
Released in 2009, the Serpent Monte Carlo code has established itself as a highly efficient and powe...
Nowadays, different multi-physics approaches are available, in order to improve the reactor safety a...
In nuclear reactor analysis, a relevant challenge is to achieve a suitable global description of nuc...
In coupled calculations with Monte Carlo neutronics and thermal hydraulics the Monte Carlo code is u...