This work is focused on the validation of the MCB code and its application to burn-up calculation and core optimization of the Pavia TRIGA Mark II research nuclear reactor installed at the Laboratory of Applied Nuclear Energy (LENA- University of Pavia). The validation has been performed with two different methods. The first one consists of a comparison between the code outputs and the values of the induced activity measured for some nuclides produced by neutron irradiation of natural uranium and thorium foils in the reactor experimental channels. The second one is based of the comparison of the code outputs and the results obtained solving a system of differential equations (Bateman equations) which describes the time evolution of the acti...
Aim of this work was to perform a rough preliminary evaluation of the burn-up of the fuel of TRIGA M...
The aim of this work was to develop a methodological approach based on Monte Carlo code for the neut...
A time evolution model was developed to study fuel burnup for the TRIGA Mark II reactor at the Unive...
This work is focused on the validation of the MCB code and its application to burn-up calculation an...
Knowledge of fuel composition as a function of irradiation time is of paramount importance both for ...
A methodological approach based on Monte Carlo code for the neutronic analysis of the TRIGA Mark II ...
Aim of this work was to perform a rough preliminary evaluation of the burn-up of the fuel of TRIGA M...
An advanced computational tool based on Monte Carlo code was developed for the neutronic analysis of...
An advanced computational tool based on Monte Carlo code was developed for the neutronic analysis of...
Aim of this work was to perform a rough preliminary evaluation of the burn-up of the fuel of TRIGA M...
The aim of this work was to develop a methodological approach based on Monte Carlo code for the neut...
A time evolution model was developed to study fuel burnup for the TRIGA Mark II reactor at the Unive...
This work is focused on the validation of the MCB code and its application to burn-up calculation an...
Knowledge of fuel composition as a function of irradiation time is of paramount importance both for ...
A methodological approach based on Monte Carlo code for the neutronic analysis of the TRIGA Mark II ...
Aim of this work was to perform a rough preliminary evaluation of the burn-up of the fuel of TRIGA M...
An advanced computational tool based on Monte Carlo code was developed for the neutronic analysis of...
An advanced computational tool based on Monte Carlo code was developed for the neutronic analysis of...
Aim of this work was to perform a rough preliminary evaluation of the burn-up of the fuel of TRIGA M...
The aim of this work was to develop a methodological approach based on Monte Carlo code for the neut...
A time evolution model was developed to study fuel burnup for the TRIGA Mark II reactor at the Unive...