Estimation of fission yield and cross-section for thorium-based molten salt reactor and accelerator driven system
Ozan Artun
article (Uluslararası, Hakemli) | Yazar(lar): Ozan Artun | Yıl: 2021 | Dergi/Kurum: MODERN PHYSICS LETTERS A | İndeks: WOS.SCI | DOI: 10.1142/s0217732321501479 | Anahtar Kelimeler: Accelerators, research reactors, fission reactions, neutron-induced fission, thorium — Özet: Thorium is the primary candidate fuel in Thori
Thorium is the primary candidate fuel in Thorium-based Molten Salt Reactor (TMSR) and Accelerator Driven System (ADS). However, to utilize Thorium in the reactor and accelerator systems, nuclear data in the literature are not sufficient for neutron-induced fission reaction process. Therefore, we estimated neutron fission cross-section sigma (mb), independent Y (A) and primary fission fragment yield YI(A), mass-dependent average neutron multiplicity nu(A), energy-dependent average neutron multiplicity nu(E) and neutron emission multiplicity distribution nu of 232Th for different neutron incident energy values, 1 MeV, 1.5 MeV, 3 MeV, 5.5 MeV, 7.7 MeV, 10 MeV, 14.8 MeV and 20 MeV, where the energy region is important for the reactor and accelerator systems used in the industry. The obtained results are compared with experimental data obtained from the literature and are discussed for each energy value.