The current work aims at presenting a simple model for PBM-type reactors' dynamic behavior analysis. The proposed model is based on point kinetics equations coupled with feedbacks from fuel and moderator temperatures. The temperature reactivity coefficients were obtained through MCNP code and via available experimental data. Parameters such as heat capacity and heat conductivity were carefully analyzed and the final system of equations was numerically solved. The obtained results, while in partial agreement with previously proposed models, suggest lower sensitivity to step reactivity insertion as compared to other reactor designs and inherent safety of the design
In this article, two-dimensional partial differential equations with time representation of nuclear ...
International audienceReactivity-Initiated Accidents (RIA) in nuclear reactor cores are very complex...
The mathematical modelling of a bench-scale reactor is presented. The formulation of the mass and he...
The study deals with reactivity insertion linear and non linear and/or Ramp reactivity expressed as ...
A useful model is presented that permits to predict with simple means the dynamic response of a smal...
An assessment of the coolant reactivity feedback influence on a small Lead-cooled Fast Reactor (LFR)...
In this work, the reactor kinetics capability is used to compute the design safety parameters in a P...
A simple and general procedure has been developed to determine the thermal behaviour of a reactor ba...
This paper presents a dynamic neutron transport mode, currently being implemented in the Serpent 2 M...
The application of best-estimate codes [coupled neutron kinetics (NK)/thermal hydraulics (TH)] for s...
The linear and Doppler feedback components of the regional contributions of the power-reactivity-dec...
To validate an MCNP5 model of the Missouri S&T Research Reactor (MSTR), temperature and void effects...
Consideration is given to the possibility to use changes in buoyancy as a negative reactivity feedba...
The Pebble Bed Advanced High Temperature Reactor (PB-AHTR) is a pebble fueled, liquid salt cooled, h...
This work is based on an object-oriented approach for the modeling and simulation of the reactor dyn...
In this article, two-dimensional partial differential equations with time representation of nuclear ...
International audienceReactivity-Initiated Accidents (RIA) in nuclear reactor cores are very complex...
The mathematical modelling of a bench-scale reactor is presented. The formulation of the mass and he...
The study deals with reactivity insertion linear and non linear and/or Ramp reactivity expressed as ...
A useful model is presented that permits to predict with simple means the dynamic response of a smal...
An assessment of the coolant reactivity feedback influence on a small Lead-cooled Fast Reactor (LFR)...
In this work, the reactor kinetics capability is used to compute the design safety parameters in a P...
A simple and general procedure has been developed to determine the thermal behaviour of a reactor ba...
This paper presents a dynamic neutron transport mode, currently being implemented in the Serpent 2 M...
The application of best-estimate codes [coupled neutron kinetics (NK)/thermal hydraulics (TH)] for s...
The linear and Doppler feedback components of the regional contributions of the power-reactivity-dec...
To validate an MCNP5 model of the Missouri S&T Research Reactor (MSTR), temperature and void effects...
Consideration is given to the possibility to use changes in buoyancy as a negative reactivity feedba...
The Pebble Bed Advanced High Temperature Reactor (PB-AHTR) is a pebble fueled, liquid salt cooled, h...
This work is based on an object-oriented approach for the modeling and simulation of the reactor dyn...
In this article, two-dimensional partial differential equations with time representation of nuclear ...
International audienceReactivity-Initiated Accidents (RIA) in nuclear reactor cores are very complex...
The mathematical modelling of a bench-scale reactor is presented. The formulation of the mass and he...