The environment effect arises when pin-cell homogenized parameters are generated with reflective boundary conditions. To treat it in whore-core pin-by-pin calculation, two works are summarized in this article. Firstly, by analyzing the relative errors of pin-cell homogenized group constants and the relative importance of pin-cell discontinuity factors (PDF) in each group, the importance of correcting the PDF of the thermal group is recognized. Secondly, the least-squares method for a multivariate polynomial is utilized to functionalize the relation of the thermal group PDF and the core parameters, including diffusion coefficient, removal cross-section, neutron source, and normalized surface flux. The C5G7 and KAIST benchmarks are employed t...
The author of this paper recently proposed a Monte Carlo calculation algorithm to solve a complex tr...
This work presents a whole-core benchmark problem based on a 2-loop pressurized water reactor with b...
The need to solve larger-scale and highly heterogeneous reactor problems is urgent nowadays; differe...
For practical reactor core applications low-order transport approximations such as SP3 have been sho...
Physical calculations of reactor cores are fundamental for reactor core design and nuclear safety an...
This thesis presents a systematic study on the merits and limitations on using pin-by-pin resolution...
There exists an interest in performing full core pin-by-pin computations for present nuclear reacto...
For practical reactor core applications, low-order transport approximations such as SP(3) have been ...
International audienceIn order to better optimise the fuel energy efficiency and perform safety anal...
Since the 80’s, industrial core calculations employ the two-step scheme based on prior cross section...
A pin power reconstruction method that is readily applicable to multigroup problems with superior ac...
Currently, safety analyses mostly rely on codes which solve both the neutronics and the thermal-hydr...
Simulations of the relative pin power distribution in a nuclear fuel assembly have been performed us...
The neutron transport equation describes the distribution of neutrons inside a nuclear reactor core....
International audienceIn the framework of the CEA scientific research on multiphysics and multiscale...
The author of this paper recently proposed a Monte Carlo calculation algorithm to solve a complex tr...
This work presents a whole-core benchmark problem based on a 2-loop pressurized water reactor with b...
The need to solve larger-scale and highly heterogeneous reactor problems is urgent nowadays; differe...
For practical reactor core applications low-order transport approximations such as SP3 have been sho...
Physical calculations of reactor cores are fundamental for reactor core design and nuclear safety an...
This thesis presents a systematic study on the merits and limitations on using pin-by-pin resolution...
There exists an interest in performing full core pin-by-pin computations for present nuclear reacto...
For practical reactor core applications, low-order transport approximations such as SP(3) have been ...
International audienceIn order to better optimise the fuel energy efficiency and perform safety anal...
Since the 80’s, industrial core calculations employ the two-step scheme based on prior cross section...
A pin power reconstruction method that is readily applicable to multigroup problems with superior ac...
Currently, safety analyses mostly rely on codes which solve both the neutronics and the thermal-hydr...
Simulations of the relative pin power distribution in a nuclear fuel assembly have been performed us...
The neutron transport equation describes the distribution of neutrons inside a nuclear reactor core....
International audienceIn the framework of the CEA scientific research on multiphysics and multiscale...
The author of this paper recently proposed a Monte Carlo calculation algorithm to solve a complex tr...
This work presents a whole-core benchmark problem based on a 2-loop pressurized water reactor with b...
The need to solve larger-scale and highly heterogeneous reactor problems is urgent nowadays; differe...