Results 21 to 30 of about 2,115,275 (370)

Advance in and prospect of moderator materials for space nuclear reactors

open access: yesInternational Journal of Energy Research, 2021
Since 1960s, many countries led by the United States and Russia have done a lot of research on space nuclear reactor power. Moderator is an important functional component in a nuclear reactor operating with a thermal neutron spectrum.
Zhihui Wang   +5 more
semanticscholar   +1 more source

Accuracy Evaluation of Image Processing Method for the Measurement of Rising Bubble Volume in Stagnant Fluid

open access: yesJournal 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
doaj   +1 more source

Potential of application of IRT-T research reactor as the solution of the problem of graphite radwaste disposal [PDF]

open access: yesNuclear Energy and Technology, 2018
Aspects of handling irradiated graphite during decommissioning uranium-graphite reactors (UGR) of different types were investigated. It was demonstrated that handling reactor graphite is complicated by the presence in the composition of graphite of long ...
Alexander Pavliuk   +3 more
doaj   +3 more sources

Ecological foresight in the nuclear power of XXI century [PDF]

open access: yes, 2016
The access to reliable sources of energy is the key to sustainable development of mankind. The major part of the energy consumed by people is generated with a chemical reaction of fossil fuel burning.
Nosov, Y.   +3 more
core   +1 more source

Hydraulic transient simulation of primary cooling circuit in Egyptian second research reactor

open access: yesJournal 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
doaj   +1 more source

The multiscale thermal‐hydraulic simulation for nuclear reactors: A classification of the coupling approaches and a review of the coupled codes

open access: yesInternational Journal of Energy Research, 2020
Simulation is becoming increasingly important in the safety analysis of nuclear reactors nowadays. The physical phenomena in a nuclear power plant happen on three classified scales: system scale (phenomenon over the whole plant is concerned), component ...
Kanglong Zhang
semanticscholar   +1 more source

Online training and education from the VR-1 reactor—Lessons learned

open access: yesNuclear 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
doaj   +1 more source

Power upgrading of WWR-S research reactor using plate-type fuel elements part I: Steady-state thermal-hydraulic analysis (forced convection cooling mode)

open access: yesNuclear 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
doaj   +1 more source

Neutrino Oscillation Experiments at Nuclear Reactors [PDF]

open access: yes, 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

Next generation control rods for fast neutron nuclear reactors

open access: yesJournal of Physics: Conference Series, 2020
Boron carbide with different boron-10 isotope content is used in the control rods of liquid sodium-cooled fast neutron nuclear reactors as absorbing material.
V. D. Risovany, A. V. Zakharov
semanticscholar   +1 more source

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