In this study, a neutronic analysis of the Laser Inertial Fusion Reactor (LIFE) fuelled uranium and this reactor's hydrogen production potential were investigated. Neutronic calculations were performed with the help of MCNP nuclear code. As a nuclear fuel, 10 vol% uranium dioxide and as a coolant, 90 vol% natural lithium were used. In neutronic calculations, tritium breeding ratio (TBR), energy multiplication factor (M), fuel burnup (BU) and fissile fuel changes were obtained. In addition, hydrogen production potential was examined by high temperature electrolysis (HTE) method and sulfur-iodine (S-I) cycled thermochemical method of the reactor. As a consequence of the calculations, a good neutronic performance was obtained in the reactor and also it was observed that HTE method, which is the one of the hydrogen production methods, produced more hydrogen by using less power than the SI method.