Results 31 to 40 of about 12,693 (50)

Experimental tests of LiSn alloys as potential liquid metal for the divertor target in a fusion reactor

open access: yesNuclear Materials and Energy, 2017
The first experiments of exposure of a LiSn alloy (Li/Sn atomic ratio= 20/80) to a hydrogen plasma in TJ-II are here presented. Solid and liquid samples have been inserted at the edge and evidence of sample melting of a solid sample during plasma ...
F.L. Tabarés   +8 more
doaj   +1 more source

Analysis of the preliminary campaign for the PETALE program

open access: yesEPJ Nuclear Sciences & Technologies, 2023
The PETALE program aims to provide new experimental data to constrain the stainless steel nuclear data. In this frame, a preliminary measurement campaign has been performed to characterize the neutron flux in key positions of the CROCUS reactor and to ...
Laureau Axel   +5 more
doaj   +1 more source

Plasma pressure and particle loss studies in the Pilot-PSI high flux linear plasma generator

open access: yesNuclear Materials and Energy, 2017
Plasma detachment in tokamak divertors reduces the particle and power fluxes to the plasma facing components and is essential for successful operation of ITER. The linear plasma generator Pilot-PSI can produce a high density (∼1021 m−3), low temperature (
K. Ješko   +4 more
doaj   +1 more source

Reliability assessment methods to address fast transient of reactor core

open access: yesInternational Journal of Advanced Nuclear Reactor Design and Technology, 2022
In order to enhance the safety of new advanced reactors, reliability based approach to the design of thermal hydraulic system becomes necessary. In this work, “load exceeds capacity” based approach of structural reliability analysis is employed and ...
N.H. Badrun   +2 more
doaj   +1 more source

Nuclear Security Education at Pakistan Institute of Engineering and Applied Sciences (PIEAS): Current Status, Future Prospects and the Lessons Learnt

open access: yesInternational Journal of Nuclear Security, 2016
In this paper, the details of nuclear security education at Pakistan Institute of Engineering and Applied Sciences (PIEAS) have been discussed. Nuclear Security education was initiated at PIEAS as a sub-specialty of its MS Nuclear Engineering Program in ...
Tariq Majeed
doaj   +1 more source

OEDGE modeling of far-SOL tungsten impurity sources and screening in WEST

open access: yesNuclear Materials and Energy, 2022
The plasma background and impurity transport in the scrape-off layer (SOL) of the WEST tokamak are modeled for three discharges over a Psep power scan ranging between 1.5 and 2.35 MW. An extended modeling grid is used to investigate far-SOL sourcing from
J.B. Maeker   +10 more
doaj   +1 more source

Nanostructure and Magnetic Field Ordering in Aqueous Fe3O4 Ferrofluids: A Small-Angle Neutron Scattering Study

open access: yesAtom Indonesia, 2019
Despite the importance of reducing production costs, investigating the hierarchical nanostructure and magnetic field ordering of Fe3O4 ferrofluids is also important to improve its application performance.
A. Taufiq   +8 more
doaj   +1 more source

The correlation of edge plasma current, electric field and divertor condition in tokamak

open access: yesNuclear Materials and Energy, 2022
The particle transport in divertor region of current size tokamak can be affected by electric field (E) significantly through the E × B drift. The plasma current, which is associated with drifts closely, affects E.
Xuele Zhao   +5 more
doaj   +1 more source

Development of innovative steels and thermo-mechanical treatments for DEMO high operating temperature blanket options

open access: yesNuclear Materials and Energy, 2018
Among the options currently taken into account for the realization of the first DEMO reactor there are the “helium-cooled” and the “dual coolant” breeding blanket.
C. Cristalli   +5 more
doaj   +1 more source

First-principles study of helium behaviors in oxide dispersion strengthened nickel alloys

open access: yesNuclear Materials and Energy, 2022
Y-Al-O oxides are characterized to be primary nanoprecipitates in oxide dispersion strengthened (ODS) Ni-based alloys for Very High Temperature Reactor (VHTR).
Fan Jia, Yiren Wang, Yong Jiang
doaj   +1 more source

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