Defected fuel rods identification in TRIGA Reactors: The experience at the ENEA Casaccia TRIGA RC-1 reactor [PDF]
EPJ Web of Conferences, 2023 Experience in running TRIGA reactors all around the world has shown that fuel cladding failures can occur. Fission products, especially in gaseous physical form, can exit the defected fuel rods being dispersed within the water primary coolant.
Lepore L. +6 more
doaj +1 more source
Effects of Hydrogen Bonding on Nuclear Data Development of Liquid Anhydrous HF [PDF]
EPJ Web of Conferences, 2023 Anhydrous Hydrogen Fluoride (HF) at high temperatures and pressures is used to process and manufacture nuclear fuel. As HF is often used directly with uranium, correct neutron thermal scattering cross sections are crucial to criticality safety ...
Ahmed Tanvir +2 more
doaj +1 more source
Neutronic conceptual design of Tehran Research Reactor using tubular fuel [PDF]
مجله علوم و فنون هستهای, 2022 The purpose of this paper is to investigate the possibility of using fuel with annular geometry (Tubular) in Tehran research reactor (TRR) from a neutronic perspective.
M. Hasanzadeh +5 more
doaj +1 more source
Science and Technology of Nuclear Installations, 2022 Steady-state and transient analysis of reactor core under Reactivity-Initiated Accident (RIA) conditions are important for reactor operation safety. The reactor dynamics are influenced by neutronic and thermal-hydraulic aspects of the core. In this study,
Surian Pinem +4 more
doaj +1 more source
Scientific Reports, 2023 This study conducted an evaluation of the corrosion behavior of an aluminum alloy utilized in the Isfahan Miniature Neutron Source Reactor (MNSR). The component analyzed, dry channel (DC), had been exposed to radiation for 12 years in a water environment
Mojtaba Bagherzadeh +5 more
doaj +1 more source
Control Rods Reactivity Worth Measurement in a Mixed Core Heavy Water Zero Power Reactor (HWZPR) [PDF]
مجله علوم و فنون هستهای, 2018 Systems related to reactivity control in a heavy water zero power reactor (HWZPR) consist of safety rod, control rod, emergency dump, and water level measurement and regulation systems.
P Kaviani +3 more
doaj +1 more source
A SIMPLIFIED TWO-NODE COARSE-MESH FINITE DIFFERENCE METHOD FOR PIN-WISE CALCULATION WITH SP3 [PDF]
EPJ Web of Conferences, 2021 For accurate and efficient pin-by-pin core calculation of SP3 equations, a simplified two-node Coarse Mesh Finite Difference (CMFD) method with the nonlinear iterative strategy is proposed.
Zhao Wenbo +8 more
doaj +1 more source
Frontiers in Energy Research, 2023 Research and development on digital twins of nuclear power systems has focused on high-precision real-time simulation and the prediction of local complex three-dimensional fluid dynamics. Traditional computational fluid dynamics (CFD) methods cannot take
Jun Yang +7 more
doaj +1 more source
Investigating the effect of data acquisition geometry and image reconstruction method on neutron computed tomography images at Tehran Research Reactor [PDF]
مجله علوم و فنون هستهای, 2023 Neutron Computed Tomography (nCT) is one of the modern applications of research reactors. The combination of the Three-dimensional representation capability of tomographic imaging and the unique properties of neutron interaction with materials creates ...
N. Araghian +5 more
doaj +1 more source
Transient calculation on TRIGA 2000 of plate-type fuel element using RELAP5, EUREKA2/RR, and MTR-DYN codes [PDF]
Nuclear Technology and Radiation Protection, 2021 The TRIGA 2000 reactor Bandung is proposed to convert from rod-type fuel to plate-type fuel because there are no manufacturers in the world that still produce rod-type fuel.
Dibyo Sukmanto +2 more
doaj +1 more source