Neutronic investigation of the thorium-based mixed-oxide as an alternative fuel in the TRIGA Mark-II research reactor – Part I: A beginning of life calculations

• Published in: Annals of nuclear energy Vol. 140; p. 107075
• Main Authors: Kabach, Ouadie, Chetaine, Abdelouahed, Benchrif, Abdelfettah, Amsil, Hamid
• Format: Journal Article
• Language: English
• Published: Elsevier Ltd 01.06.2020
• Subjects: Alternative fuel; MCNPX2.6; Neutronic parameters; Seed-blanket; Thorium oxide; Alternative fuel; Seed-blanket; Thorium oxide; MCNPX2.6; Neutronic parameters
• ISSN: 0306-4549; 1873-2100
• DOI: 10.1016/j.anucene.2019.107075

•The characteristics of (Th,U)O2 as alternative fuel in the TRIGA Mark-II reactor were investigated.•Nine different seed-blanket configurations were optimized.•MCNPX code with the ENDF-VII.1 cross section library were used.•The new results were compared to the standard configuration.•The obtained results were encouraging but further investigations are needed. This article presents a neutronic investigation of the effect of replacing some uranium zirconium hydride (U-ZrH1.6) fuels with thorium-based mixed-oxide ((Th,U)O2) fuels in the TRIGA Mark-II research reactor without changing the core geometry, while the only variable is the fuel material. The possibility of utilizing thorium mixed oxide fuel in the TRIGA Mark-II reactor is assessed using the famous seed-blanket configuration or also known as Radkowsky Thorium Fuel (RTF) concept. Using the RTF concept, a long core lifetime can be achieved by enhancing the internal conversion rate of fertile to fissile materials, thanks to the thermal capture cross-section of 232Th that is around three times that of 238U. Additionally, on the fuel cycle aspect of using the thorium-based fuel is that the thorium cycle produces much less plutonium and other transuranic radioactive elements than uranium fuel cycle. Actually, neutronic and kinetic calculations, at the beginning of life conditions, for nine different seed-blanket configurations have been investigated using the MCNPX2.6 code. These calculations for all proposed configurations in comparison with the conventional U-ZrH1.6 fueled core were performed to pick out an optimal core(s) design ensuring the most efficient use of (Th,U)O2 fuel in it and with minimum changes in the main safety parameters. The parameters consist of effective multiplication factor keff, delayed neutron fraction βeff, neutron flux distribution, power distribution and radial hot rod power peaking factor (FHR), and shutdown margin (SDM). The calculation results exhibit that the highest initial criticality achieved is 1.07716. The results of the other neutronic investigations of thorium-based mixed-oxide fuel elements and their positions, including their numbers in the core are summarized and discussed in the following paper.