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Published in 2018 at "International Journal of Energy Research"
DOI: 10.1002/er.3759
Abstract: Summary One of the most important ITER missions is to test tritium breeding blanket (TBB) concepts that would result in tritium self-sufficiency, an extraction of high grade heat and net electricity production in future fusion…
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Keywords:
fusion;
objectives management;
iter;
tbm program ... See more keywords
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Published in 2018 at "Journal of Fusion Energy"
DOI: 10.1007/s10894-018-0202-1
Abstract: The development and design of the CXRS diagnostic for the core plasma of ITER is used as a pretext to elaborate on several of the main challenges of optical diagnostics on such a large fusion…
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Keywords:
core plasma;
plasma cxrs;
iter;
cxrs diagnostic ... See more keywords
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Published in 2019 at "Journal of Fusion Energy"
DOI: 10.1007/s10894-019-00214-8
Abstract: AbstractEighteen Toroidal Field (TF) coils are operated on steady-state mode at highest current of 68 kA in comparison with the other pulse operation coils such as Poloidal Field and Central Solenoid coils in ITER superconductive magnet…
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Keywords:
protection;
system;
field;
iter ... See more keywords
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1
Published in 2020 at "Medical Science Educator"
DOI: 10.1007/s40670-019-00855-6
Abstract: Introduction The University of Manitoba’s ambulatory pediatric clerkship transitioned to daily encounter cards (DECs) from single in-training evaluation reports (ITERs). The impact of this change on quality of student assessment was unknown. Using the validated…
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Keywords:
training;
student assessment;
evaluation;
iter ... See more keywords
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Published in 2017 at "Fusion Engineering and Design"
DOI: 10.1016/j.fusengdes.2017.02.037
Abstract: Abstract This paper mainly introduces the seismic analysis of the high-power dc reactor prototype, whose functions are to limit the ripple current and the increasing rate of fault current in the ITER poloidal field (PF)…
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Keywords:
high power;
analysis;
seismic analysis;
iter ... See more keywords
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Published in 2017 at "Fusion Engineering and Design"
DOI: 10.1016/j.fusengdes.2017.02.102
Abstract: Abstract This paper presents the ongoing R&D research activities at IRSN related to the improvement of the properties of dust solid phases. It is illustrated by an ASTEC simulation of a wet-bypass scenario in the…
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Keywords:
speciation case;
evaluation dust;
contribution better;
dust speciation ... See more keywords
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Published in 2017 at "Fusion Engineering and Design"
DOI: 10.1016/j.fusengdes.2017.05.014
Abstract: Abstract In ITER blanket system, electrical connectors (“E–straps”, ES) are used to form a low impedance electrical path from shield blocks (SB) to the vacuum vessel (VV). Main functions of ES is providing current from…
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Keywords:
analysis experimental;
iter blanket;
experimental justification;
iter ... See more keywords
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Published in 2017 at "Fusion Engineering and Design"
DOI: 10.1016/j.fusengdes.2017.05.075
Abstract: Abstract The ITER plasma position reflectometry (PPR) system measures the edge electron density profile of the plasma, providing real-time supplementary contribution to the magnetic measurements of the plasma-wall distance. The reflectometry antenna is one of…
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Keywords:
reflectometry antenna;
plasma position;
iter;
position reflectometry ... See more keywords
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Published in 2017 at "Fusion Engineering and Design"
DOI: 10.1016/j.fusengdes.2017.06.022
Abstract: The ITER Central Solenoid (CS) is one of the critical elements of the machine. The CS conductor went through an intense optimization and qualification program, which included characterization of the strands, a conductor straight short…
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Keywords:
conductor;
iter;
performance;
characterization iter ... See more keywords
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Published in 2018 at "Fusion Engineering and Design"
DOI: 10.1016/j.fusengdes.2017.12.042
Abstract: Abstract A TE31,11 mode gyrotron has being developed to improve the output power for the ITER electron cyclotron (EC) system. Strong mode competition having counter-rotating modes in both the high and/or low field sides is,…
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Keywords:
mode;
gyrotron;
te31 mode;
high order ... See more keywords
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Published in 2018 at "Fusion Engineering and Design"
DOI: 10.1016/j.fusengdes.2018.01.074
Abstract: Abstract A model predictive control (MPC) scheme for ITER plasma current and shape controller (PCSC) is presented. The controller is able to control a large number of geometrical plasma shape descriptors using output-space reduction based…
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Keywords:
model predictive;
shape;
control;
iter ... See more keywords