Results 11 to 20 of about 1,705,201 (196)

Defected fuel rods identification in TRIGA Reactors: The experience at the ENEA Casaccia TRIGA RC-1 reactor [PDF]

open access: yesEPJ 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]

open access: yesEPJ 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

Monitoring a gas-cooled nuclear reactor core integrity [PDF]

open access: yes, 2008
This work concerns with the problem of monitoring an Advanced Gas-cooled Nuclear Reactor (AGR) core. In the world wide context of energy production, the advanced gas-cooled reactor (AGR) nuclear power stations are approaching the end of their predicted ...
Grimble, Michael J.   +4 more
core   +4 more sources

An Improved Steady-State and Transient Analysis of the RSG-GAS Reactor Core under RIA Conditions Using MTR-DYN and EUREKA-2/RR Codes

open access: yesScience 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

Long-time irradiation effect on corrosion behavior of aluminum alloy in pool water of low-power research reactor

open access: yesScientific 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

Neutronic conceptual design of Tehran Research Reactor using tubular fuel [PDF]

open access: yesمجله 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

Condition monitoring of an advanced gas-cooled nuclear reactor core [PDF]

open access: yes, 2007
A critical component of an advanced gas-cooled reactor station is the graphite core. As a station ages, the graphite bricks that comprise the core can distort and may eventually crack.
Giovanini, L.   +3 more
core   +4 more sources

Control Rods Reactivity Worth Measurement in a Mixed Core Heavy Water Zero Power Reactor (HWZPR) [PDF]

open access: yesمجله 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

Fast prediction of compressor flow field in nuclear power system based on proper orthogonal decomposition and deep learning

open access: yesFrontiers 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

A SIMPLIFIED TWO-NODE COARSE-MESH FINITE DIFFERENCE METHOD FOR PIN-WISE CALCULATION WITH SP3 [PDF]

open access: yesEPJ 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

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