This paper describes the built-in calculation routines in the reactor physics code Serpent 2 that provide a novel method for solving the coupled problem of the power distribution, temperature distribution, and material property distributions in nuclear fuel elements. All of the coupled distributions are solved during a single simulation with no coupling to external codes. The temperature feedback system consists of three separate built-in parts: an explicit treatment of the thermal motion of target nuclides during the transport calculation, an internal analytic radial temperature profile solver, and internal material property correlations. The internal structure and couplings of the calculation routines are described in detail, after which ...
This article describes the implementation of a burnup scheme with coupled fuel behavior feedback int...
Released in 2009, the Serpent Monte Carlo code has established itself as a highly efficient and powe...
In nuclear reactor analysis, a relevant challenge is to achieve a suitable global description of nuc...
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...
This paper describes the recent developments in the multi-physics capabilities of the Serpent Monte ...
This paper presents a dynamic neutron transport mode, currently being implemented in the Serpent 2 M...
The increasing interest in high fidelity modeling of power and test reactors drives the development ...
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...
Precise simulation of the isotopic composition of nuclear fuel and temperatures during reactor opera...
Modeling nuclear reactors is complex, requiring multiphysics solutions between neutronics, thermal h...
In nuclear reactors, fuel burnup calculations assess the time evolution of both the fuel composition...
The main goal of this work was to couple the Monte Carlo neutronics code Serpent~2 with a CFD solver...
This article describes the implementation of a burnup scheme with coupled fuel behavior feedback int...
Released in 2009, the Serpent Monte Carlo code has established itself as a highly efficient and powe...
In nuclear reactor analysis, a relevant challenge is to achieve a suitable global description of nuc...
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...
This paper describes the recent developments in the multi-physics capabilities of the Serpent Monte ...
This paper presents a dynamic neutron transport mode, currently being implemented in the Serpent 2 M...
The increasing interest in high fidelity modeling of power and test reactors drives the development ...
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...
Precise simulation of the isotopic composition of nuclear fuel and temperatures during reactor opera...
Modeling nuclear reactors is complex, requiring multiphysics solutions between neutronics, thermal h...
In nuclear reactors, fuel burnup calculations assess the time evolution of both the fuel composition...
The main goal of this work was to couple the Monte Carlo neutronics code Serpent~2 with a CFD solver...
This article describes the implementation of a burnup scheme with coupled fuel behavior feedback int...
Released in 2009, the Serpent Monte Carlo code has established itself as a highly efficient and powe...
In nuclear reactor analysis, a relevant challenge is to achieve a suitable global description of nuc...