Results 1 to 10 of about 359,095 (284)

One-dimensional Modelling and Optimisation of an Industrial Steam Methane Reformer [PDF]

open access: yesChemical and Biochemical Engineering Quarterly, 2022
Steam methane reforming is one of the most promising processes to convert natural gas into valuable products such as hydrogen. In this study, a one-dimensional model was used to model and optimise an industrial steam methane reformer, using mass and ...
M. Sinaei Nobandegani   +5 more
doaj   +1 more source

SENSITIVITY ANALYSIS OF STAINLESS STEEL REFLECTOR FOR VR-1 TRAINING REACTOR [PDF]

open access: yesEPJ Web of Conferences, 2021
Pressurized water reactors are typically surrounded in the radial direction by neutron reflectors made from stainless steel and water. These reflectors decrease neutron leakage and provide protection of pressure vessel from fast neutrons damaging its ...
Frybort Jan   +4 more
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

Designing Stainless Steel Reflector at VR-1 Training Reactor [PDF]

open access: yesEPJ Web of Conferences, 2020
Light-water reactor cores are commonly surrounded by a stainless steel and water reflector. The reflectors are improving power distribution in the core, reducing the leakage of neutrons and thus also protecting the pressurized vessel from the neutron ...
Frybort Jan, Suk Pavel, Fejt Filip
doaj   +1 more source

Uranium recovery from laboratory wastewater in phosphoric acid medium [PDF]

open access: yesمجله علوم و فنون هسته‌ای, 2020
In SOOREH Co, a significant amount of uranium-containing phosphoric acid wastewater from analytical operations is produced on a large volume of process samples.
K. Fatemi, M. Habibi Zare, H. Vakili
doaj   +1 more source

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

Numerical study of the closure flow within the chimney of a typical MTR reactor

open access: yesInternational Journal of Thermofluids, 2020
In this work, the closure flow values effect on the penetration depth of radioactive water inside the core chimney of a typical MTR reactor is studied numerically using commercial CFD software ANSYS FLUENT.
Salah El-Din El-Morshedy   +2 more
doaj   +1 more source

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

The BFS complex – a unique facility to justify the neutronic parameters of the new generation fast reactor cores [PDF]

open access: yesNuclear Energy and Technology, 2022
The BFS complex comprising two fast critical facilities – BFS-1 and BFS-2 – is a unique experimental base for research into fast reactor physics, reactor safety, core optimization, justification of the closed fuel cycle parameters.
Sergey M. Bednyakov   +6 more
doaj   +3 more sources

About chemical form and binding energy of 14C in irradiated graphite of uranium-graphite nuclear reactors [PDF]

open access: yesNuclear Energy and Technology, 2018
Issues associated with handling irradiated graphite of uranium-graphite nuclear reactors are examined. It is demonstrated that selection of approaches, methods and means for handling irradiated graphite are determined by the form of occurrence and ...
Evgeny V. Bespala   +3 more
doaj   +3 more sources

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