Results 11 to 20 of about 143,089 (299)
Journal of Fluid Science and Technology, 2013 The measurement error when calculating the bubble volume by using image analysis was estimated by taking a single bubble of known volume (0.02 × 10-6-2.00 × 10-6 m3, or the volume equivalent diameter of 3.37-15.63 mm) and using a stereo ...
Noriaki INABA +2 more
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Hydraulic transient simulation of primary cooling circuit in Egyptian second research reactor
Journal of King Saud University: Engineering Sciences, 2022 Hydraulic transient is a flow situation where the velocity of the flow and the pressure change rapidly with time in pipes networks filled with fluid. Water hammer is one of the consequences that may occur accidentally in the reactors cooling system.
Hesham Elkhatib +2 more
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Online training and education from the VR-1 reactor—Lessons learned
Nuclear Engineering and Technology, 2023 Hands-on education and training is a key part of fixing and developing technology knowledge and is an inherent part of many engineering and scientific curricula.
Ondrej Novak +5 more
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Neutrino Oscillation Experiments at Nuclear Reactors [PDF]
, 1999 In this paper I give an overview of the status of neutrino oscillation experiments performed using nuclear reactors as sources of neutrinos. I review the present generation of experiments (Chooz and Palo Verde) with baselines of about 1 km as well as the
Achkar +12 more
core +3 more sources
Nuclear Engineering and Technology, 2020 The design of a nuclear reactor core requires basic thermal-hydraulic information concerning the heat transfer regime at which onset of nucleate boiling (ONB) will occur, the pressure drop and flow rate through the reactor core, the temperature and power
Adel Alyan, Moustafa S. El-Koliel
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EPJ Web of Conferences, 2015 The neutron capture cross sections and the capture γ-ray spectra of 138Ba were measured in the astrophysically important energy region. Measurements were made at neutron energies from 15 to 80 keV.
Katabuchi T. +4 more
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Journal of Thermal Science and Technology, 2013 For predicting the void fraction distribution in subcooled flow boiling, it is necessary to measure the interfacial heat transfer coefficient—which determines the amount of condensation rate of vapor bubble—with high accuracy.
Noriaki INABA +2 more
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Geometry Optimization of Dispersed UMo Fuel for Light Water Reactors
Nuclear Engineering and Technology, 2023 The Uranium/Molybdenum metallic fuel has been proposed as promising advanced fuel concept especially in the dispersed fuel geometry. The fuel is manufactured in the form of small fuel droplets (particles) placed in a fuel pin covered by a matrix.
Ondrej Novak +3 more
doaj +1 more source
Testing of the ABBN-RF multigroup data library in photon transport calculations
EPJ Web of Conferences, 2017 Gamma radiation is produced via both of nuclear fuel and shield materials. Photon interaction is known with appropriate accuracy, but secondary gamma ray production known much less. The purpose of this work is studying secondary gamma ray production data
Koscheev Vladimir +3 more
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Application of the Source-Jerk method using a neutron generator in a subcritical reactor
Acta Polytechnica, 2023 This paper describes the application of the Source-Jerk method using a neutron generator in the VR-1 reactor. The experiments were carried out on a shutdown reactor with subcriticality greater than -10 βeff.
Jan Rataj, Jakub Mátl, Pavel Suk
doaj +1 more source