Main aim of this study is to investigate hydrogen production potential of Advanced Power EXtraction (APEX) fusion reactor cooled with the molten-salt mixtures, as well as its neutronic performance to transmute minor actinides (MAs). In the original APEX reactor concept, fusion power (P f ) is quite high (4000 MW), and the FLiBe molten-salt flows as molten-salt wall. The FLiBe molten-salt is mixed with molten minor actinide tetra fluoride salt (MAF 4 ) to transmute minor actinides, and at the same time, to increase the energy multiplication. In addition to this mixture of FLiBe and MAF 4 , FLiNaBe, LiF and Eutectic Lithium instead of FLiBe are mixed individually with MAF 4 , and are used as the molten-salt coolant. Furthermore, two different compositions of MA nuclides are considered as follows: (i) The MA nuclides discharged from the pressured water reactor (PWR)-MOX spent fuel and (ii) The MA nuclides discharged from the PWR-UO 2 spent fuel. The neutronic analyses have been performed for these eight different molten-salt mixture cases and for both one and three-dimensional geometry models by using the XSDRNPM/SCALE4.4a neutron transport code and the MCNP4B code, respectively.
In order to produce hydrogen in large-scale, Steam-Methane Reforming (SMR) combined with the Mineral CO 2 Sequestration (MCS) is selected. Furthermore, the sulfureiodine (SeI) thermochemical water splitting and high-temperature electrolysis (HTE) cycles, which are the most promising water-splitting cycles, are analyzed. The results of calculations bring out that the considered fusion reactor has a good neutronic performance, and it can produce in a considerable amount of the hydrogen production (up to 426 kg/s), as well as the minor actinide transmutation (up to 4.849 t/yr).