@article{JPT, author = {Piotr Mazgaj and Piotr Darnowski and Sebastian Gurgacz and Maciej Lipka and Karolina Dziubanii}, title = { Comparison of Simple Design of Sodium and Lead Cooled Fast Reactor Cores}, journal = {Journal of Power Technologies}, volume = {94}, number = {5}, year = {2014}, keywords = {lead fast reactor; sodium fast reactor; pin design; MCNP}, abstract = {Abstract The purpose of this report was to present the results of a numerical simulation of thermal hydraulics processes in the liquid metal cooled fast reactor core, combined with the simple neutron population computing for infinite pin cell lattice. Two types of the coolant have been studied: liquid sodium and the liquid lead, with all requirements regarded to safety conditions. Temperature distributions along the cooling channel and distributions in radial direction have been prepared and in the next step the criticality calculations using MCNP Monte Carlo code for MOX fuel have been conducted.}, issn = {2083-4195}, pages = {16--26}, url = {https://papers.itc.pw.edu.pl/index.php/JPT/article/view/394} }