naa a22 4500 510766579 CHVBK 20180411083158.0 cr unu---uuuuu 180411e20130101xx s 000 0 eng 10.1007/s12043-012-0462-7 doi (NATIONALLICENCE)springer-10.1007/s12043-012-0462-7 Neutronic simulation of a research reactor core of (232Th, 235U)O 2 fuel using MCNPX2.6 code [Elektronische Daten] [SEYED FEGHHI, MARZIEH REZAZADEH, YACINE KADI, CLAUDIO TENREIRO, MORTEZA AREF, ZOHREH GHOLAMZADEH] The small reactor design for the remote and less developed areas of the user countries should have simple features in view of the lack of infra-structure and resources. Many researchers consider long core life with no on-site refuelling activity as a primary feature for the small reactor design. Long core life can be achieved by enhancing internal conversion rate of fertile to fissile materials. For that purpose, thorium cycle can be adopted because a high fissile production rate of 233U converted from 232Th can be expected in the thermal energy region. A simple nuclear reactor core arranged 19 assemblies in hexagonal structure, using thorium-based fuel and heavy water as coolant and moderator was simulated using MCNPX2.6 code, aiming an optimized critical assembly. Optimized reflector thickness and gap between assemblies were determined to achieve minimum neutron leakage and void reactivity. The result was a more compact core, where assemblies were designed having 19-fuel pins in 1.25 pitch-to-diameter ratio. Optimum reflector thickness of 15 cm resulted in minimal neutron leakage in view of economic limitations. A 0.5 cm gap between assembles achieved more safety and 2.2% enrichment requirements. The present feasibility study suggests a thermal core of acceptable neutronic parameters to achieve a simple and safe core. Indian Academy of Sciences, 2012 Critical nationallicence MCNPX2.6 nationallicence reactor core nationallicence thorium oxide nationallicence FEGHHI SEYED Department of Radiation Application, Shahid Beheshti University, Tehran, G.C, Iran aut REZAZADEH MARZIEH Nuclear Science and Technology Research Institute, Tehran, Iran aut KADI YACINE European Organization for Nuclear Research, CERN, 1211, Geneva 23, Switzerland aut TENREIRO CLAUDIO Department of Energy Science, Sungkyunkwan University, 300, Cheoncheon-dong, Suwon, Korea aut AREF MORTEZA Faculty of Engineering, Research and Science Branch, Zanjan University, Zanjan, Iran aut GHOLAMZADEH ZOHREH Talca University, St. 720-747, Talca, Chile aut Pramana Springer-Verlag 80/1(2013-01-01), 105-120 0304-4289 80:1<105 2013 80 12043 https://doi.org/10.1007/s12043-012-0462-7 text/html Onlinezugriff via DOI 1 research-article jats NATIONALLICENCE 856 40 https://doi.org/10.1007/s12043-012-0462-7 text/html Onlinezugriff via DOI NATIONALLICENCE 700 1- FEGHHI SEYED Department of Radiation Application, Shahid Beheshti University, Tehran, G.C, Iran aut NATIONALLICENCE 700 1- REZAZADEH MARZIEH Nuclear Science and Technology Research Institute, Tehran, Iran aut NATIONALLICENCE 700 1- KADI YACINE European Organization for Nuclear Research, CERN, 1211, Geneva 23, Switzerland aut NATIONALLICENCE 700 1- TENREIRO CLAUDIO Department of Energy Science, Sungkyunkwan University, 300, Cheoncheon-dong, Suwon, Korea aut NATIONALLICENCE 700 1- AREF MORTEZA Faculty of Engineering, Research and Science Branch, Zanjan University, Zanjan, Iran aut NATIONALLICENCE 700 1- GHOLAMZADEH ZOHREH Talca University, St. 720-747, Talca, Chile aut NATIONALLICENCE 773 0- Pramana Springer-Verlag 80/1(2013-01-01), 105-120 0304-4289 80:1<105 2013 80 12043 Metadata rights reserved Springer special CC-BY-NC licence nationallicence BK010053 XK010053 XK010000 NATIONALLICENCE NATIONALLICENCE NL-springer