Übeyli, M.2019-02-042019-02-042006Übeyli, M. (2006). On the neutronic analysis of a fusion reactor with different thorium molten salts. The Fourth Eurasian Conference on Nuclear Science and Its Application : Presentations, (s. 96-102). 31 October- 3 November 2006. Baku, Azerbaijan.http://kurumsalarsiv.tenmak.gov.tr/handle/20.500.12878/1041Controlled nuclear fusion serves inexhaustible energy to mankind. However, there is still a long way for the market penetration of commercial fusion reactor with high energy gain. On the other hand a fusion breeder can operate commercially due to the fissile fuel production in addition to higher energy multiplication. HYLIFE-II is one of the major inertial fusion energy reactor design concepts in which a thick molten salt layer (Flibe = Li2BeF4) is injected between the reaction chamber walls and the explosions. In this type of reactor, molten salt coolant annihilates the frequent replacement of solid first wall structure during reactors lifetime. In this study, the neutronic analysis of HYLIFE-II fusion reactor with different liquid wall coolants, namely, 75% LiF-25% ThF4, 75% LiF-24% ThF4-l% 233UF4 or 75% LiF-23% ThF4-2% 233UF4 was investigated. In order to get neutron spectra distribution in the reactor, neutron transport calculations were carried out using the code, Scale4.3 by solving the Boltzmann transport equation in S8-P3 approximation. The main objective of this study was to examine the effect of flowing liquid wall thickness and type of coolant on the neutronic performance of the reactor. In addition, radiation damage calculations at the first wall structure with respect to type and thickness of the liquid wall were made. It was shown that using the flowing liquid wall containing the molten salt 75% LiF-23% ThF4-2% UF4 with a thickness of ~ 70 cm maintained tritium self-sufficiency of the (DT) fusion driver and extended the first wall lifetime to the reactor’s lifetime (~30 full power years). Furthermore significant amount of high quality fissile fuel 233U was produced through (n,y) reaction of 232Th. Moreover, energy multiplication factor, (M) was increased very much by the high rate fission reactions of 233U occurred in the flowing wall. On the other hand, using other two coolants, 75% LiF- 25% ThF4 or 75% LiF-24% ThF4-l% 233UF4 as a liquid wall did not satisfied the radiation damage and the tritium sufficiency criteria together at any thickness so that these two coolants were not suitable to improve neutronic performance of HYLIFE-II reactor.enginfo:eu-repo/semantics/openAccessNeutronic analysisNötronik analizThoriumToryumMolten saltsErimiş tuzlarFusion reactorFüzyon reaktörOn the neutronic analysis of a fusion reactor with different thorium molten saltsconferenceObject96102