Add to ORKGCarreño, A.; Vidal-Ferràndiz, A.; Ginestar Peiro, D.; Verdú Martín, GJ. (2019). Adaptive modal methods to integrate the neutron diffusion equation. R. Company, J. C. Cortés, L. Jódar and E. López-Navarro. 26-31. http://hdl.handle.net/10251/180549263
Reactivity insertion accidents are one of the design-basis accidents that drive nuclear reactor limi...
A method, called the higher mode synthesis method, for the solution of the two-dimensional neutron d...
[EN] Given a configuration of a nuclear reactor core, the neutronic distribution of the power can be...
[EN] The distribution of the power inside a reactor core can be described by the time dependent mult...
[EN] The solution of the time-dependent neutron diffusion equation can be approximated using quasi-s...
The distribution of the power inside a reactor core can be described by the time dependent multigrou...
Multiphysics coupling is becoming of large interest in the nuclear engineering and computational sci...
La ecuación de la difusión neutrónica describe la población de neutrones de un reactor nuclear. Este...
The different neutronic parameters have to be calculated with a higher accuracy in order to design t...
To simulate the behaviour of a nuclear power reactor it is necessary to be able to integrate the tim...
AbstractWe study iterative methods for solving linear systems arising in the discretization of the t...
Numerical solution of the neutron diffusion equation : adaptive concepts in time and space / Werner ...
Dans cette thèse nous avons tout d'abord développé un solveur neutronique de cinétique transport 3D ...
This paper continues our treatment of the Neutron Transport Equation (NTE) building on the work in [...
Time-dependent nuclear reactor simulations are essential in improving the safety, effectiveness, and...
Reactivity insertion accidents are one of the design-basis accidents that drive nuclear reactor limi...
A method, called the higher mode synthesis method, for the solution of the two-dimensional neutron d...
[EN] Given a configuration of a nuclear reactor core, the neutronic distribution of the power can be...
[EN] The distribution of the power inside a reactor core can be described by the time dependent mult...
[EN] The solution of the time-dependent neutron diffusion equation can be approximated using quasi-s...
The distribution of the power inside a reactor core can be described by the time dependent multigrou...
Multiphysics coupling is becoming of large interest in the nuclear engineering and computational sci...
La ecuación de la difusión neutrónica describe la población de neutrones de un reactor nuclear. Este...
The different neutronic parameters have to be calculated with a higher accuracy in order to design t...
To simulate the behaviour of a nuclear power reactor it is necessary to be able to integrate the tim...
AbstractWe study iterative methods for solving linear systems arising in the discretization of the t...
Numerical solution of the neutron diffusion equation : adaptive concepts in time and space / Werner ...
Dans cette thèse nous avons tout d'abord développé un solveur neutronique de cinétique transport 3D ...
This paper continues our treatment of the Neutron Transport Equation (NTE) building on the work in [...
Time-dependent nuclear reactor simulations are essential in improving the safety, effectiveness, and...
Reactivity insertion accidents are one of the design-basis accidents that drive nuclear reactor limi...
A method, called the higher mode synthesis method, for the solution of the two-dimensional neutron d...
[EN] Given a configuration of a nuclear reactor core, the neutronic distribution of the power can be...