Results 1 to 10 of about 50,199,216 (303)

Editorial: Novel nuclear reactors and research reactors

open access: yesFrontiers in Energy Research
Shichang Liu   +4 more
doaj   +4 more sources

Challenge for the validation of high-fidelity multi-physics LWR modeling and simulation: Development of new experiments in research reactors

open access: yesFrontiers in Energy Research, 2023
Current approaches to validate multi-physics coupling mainly rely upon experimental data from the operation of the current reactor fleet. These data allow global experimental validation based on Light Water Reactor (LWR) macroscopic physical parameters ...
Claire Vaglio-Gaudard   +7 more
doaj   +3 more sources

Gamma-ray Spectroscopy in Low-Power Nuclear Research Reactors

open access: yesJournal of Nuclear Engineering
Gamma-ray spectroscopy is an effective technique for radioactive material characterization, routine inventory verification, nuclear safeguards, health physics, and source search scenarios.
Oskari V. Pakari   +8 more
doaj   +3 more sources

REACTOR PERFORMANCE IMPROVEMENT OPTIONS TO SUSTAIN HIGH FLUX ISOTOPE REACTOR LEADERSHIP INTO THE FUTURE* [PDF]

open access: yesEPJ Web of Conferences, 2021
The mission of the Neutron Sciences Directorate (NScD) at the U.S. Department of Energy’s Oak Ridge National Laboratory (ORNL) is the undertaking of high-impact research into the structure and properties of materials across the spectrum of biology ...
Chandler D., Betzler B. R., Cook D. H.
doaj   +1 more source

Outcomes of the “steady-state crisis” experiment in the MIR reactor channel [PDF]

open access: yesNuclear Energy and Technology, 2019
To license nuclear fuel for nuclear power plants, data on the behavior of fuel elements (FE) under design-basis accidents are required. These data are obtained during tests of fuel assemblies (FA) and single fuel elements in research reactor channels ...
Aleksandr V. Alekseev   +4 more
doaj   +3 more sources

Measurement of the spent fuel rod cladding temperature during the in-pile testing at 500–900°C [PDF]

open access: yesNuclear Energy and Technology, 2018
This paper deals with the problem of measuring the VVER-1000 burnup fuel cladding temperature in a 500–900°C range in the process of experiments in a channel of the MIR research reactor to obtain data on the fuel element behavior under the influence of ...
Oleg I. Dreganov   +3 more
doaj   +3 more sources

Regulation of the temperature in the ampoule channel with natural circulation of coolant [PDF]

open access: yesNuclear Energy and Technology, 2018
It has been shown by calculations that it is possible to extend considerably the capabilities for control of temperature conditions in an ampoule channel with natural coolant circulation, using the proposed hydraulic circuit layout, on samples during ...
Tatiana Osipova   +2 more
doaj   +3 more sources

CONCEPTUAL FUEL ELEMENT DESIGN CANDIDATES FOR CONVERSION OF HIGH FLUX ISOTOPE REACTOR WITH LOW-ENRICHED URANIUM SILICIDE DISPERSION FUEL* [PDF]

open access: yesEPJ Web of Conferences, 2021
Engineering design studies are underway to assess the feasibility of converting the High Flux Isotope Reactor (HFIR) to operate with low-enriched uranium silicide dispersion (LEU3Si2-Al) fuel. These studies are supported by the U.S.
Chandler D.   +4 more
doaj   +1 more source

INVAP′s Research Reactor Designs [PDF]

open access: yesScience and Technology of Nuclear Installations, 2010
INVAP, an Argentine company founded more than three decades ago, is today recognized as one of the leaders within the research reactor industry. INVAP has participated in several projects covering a wide range of facilities, designed in accordance with the requirements of our different clients.
Villarino, Eduardo, Doval, Alicia
openaire   +2 more sources

The Concept of the Heat Removal System of a High-Flux Research Reactor

open access: yesScience and Technology of Nuclear Installations, 2022
Achieving high neutron fluxes in research pressurized water reactors is directly related to the intensity of the coolant flow through the core and the pressure in it, which provides an increased saturation temperature and a margin to critical heat flux ...
Vitaly Uzikov   +2 more
doaj   +1 more source

Home - About - Disclaimer - Privacy