Search Results - "Pitcher, C.S."
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1
ITER hot Cell—Remote handling system maintenance overview
Published in Fusion engineering and design (01-11-2017)“…ITER is a large scale fusion device designed to study the high temperature fusion reaction between tritium and deuterium. The success of a tokamak-type fusion…”
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2
Radwaste management aspects of the test blanket systems in ITER
Published in Fusion engineering and design (01-11-2016)“…•Test Blanket Systems are operated in ITER to test tritium breeding technologies.•The in-vessel parts of TBS become radio-active during the ITER nuclear…”
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3
Final design of the generic equatorial port plug structure for ITER diagnostic systems
Published in Fusion engineering and design (01-10-2015)“…The Diagnostic Generic Equatorial Port Plug (GEPP) is designed to be common to all equatorial port-based diagnostic systems. It is designed to survive…”
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4
Neutronics for equatorial and upper ports in ITER
Published in Fusion engineering and design (01-10-2013)“…•ITER neutronics calculations for Diagnostic Equatorial Port Plug (EPP) and Electron Cyclotron Heating Upper Launcher (ECHUL).•Activation and radiation…”
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5
Integration of remote refurbishment performed on ITER components
Published in Fusion engineering and design (01-10-2015)“…•System engineering approach to consolidate requirements to modify the layout of the Hot Cell.•Illustration of the loop between requirement and…”
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6
Support structure concept for integration of ITER diagnostics in the port cell
Published in Fusion engineering and design (01-10-2013)“…► An interspace support structure to support the diagnostic systems from the back of the upper and equatorial port plugs to the biological shield plug. ► Port…”
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7
Visible imaging of turbulence in the SOL of the Alcator C-Mod tokamak
Published in Journal of nuclear materials (01-03-2001)“…Measurements of fluctuations in the scrape-off layer (SOL) of Alcator C-Mod plasmas were made using visible emission from the plasma edge. Line emissions from…”
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8
Toroidal rotation as an explanation for plasma flow observations in the Alcator C-Mod scrape-off layer
Published in Journal of nuclear materials (01-03-2003)“…Parallel and E× B plasma flows near the separatrix on the outside midplane of Alcator C-Mod are investigated with a scanning probe for a range plasma…”
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9
Study of gross and net erosion in the ASDEX upgrade divertor
Published in Journal of nuclear materials (01-02-1997)“…Erosion of carbon and tungsten in the divertor of ASDEX Upgrade was investigated by surface analysis of target tile probes. The probes were exposed in the…”
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10
A novel tracer-gas injection system for scrape-off layer impurity transport and screening experiments
Published in Journal of nuclear materials (01-03-1999)“…The design, operation, and initial results of a novel tracer-gas injection system is described. This system has been developed to diagnose local impurity…”
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11
Monte Carlo radiation shielding and activation analyses for the Diagnostic Equatorial Port Plug in ITER
Published in Fusion engineering and design (01-08-2012)“…► Systematic neutronics analyses were conducted to assess the ITER Equatorial Port Plug radiation shielding performance. ► Shielding optimization was achieved…”
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12
Electromagnetic analysis of ITER diagnostic equatorial port plugs during plasma disruptions
Published in Fusion engineering and design (01-10-2013)“…► Disruption loads on ITER diagnostic equatorial port plugs are extracted. ► Upward major disruption produces the largest radial moment and radial force on…”
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13
Plasma profiles and flows in the high-field side scrape-off layer in Alcator C-Mod
Published in Journal of nuclear materials (01-03-2005)“…A novel, magnetically-driven swing probe was recently installed near the midplane on the high-field side SOL in Alcator C-Mod. The probe collects plasma from…”
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14
The remote handling compatibility analysis of the ITER generic upper port plug structure
Published in Fusion engineering and design (01-10-2014)“…•We describe the remote handling compatibility of the ITER generic upper port plug.•Concepts are presented of specific design solutions to improve RH…”
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15
Nuclear engineering of diagnostic port plugs on ITER
Published in Fusion engineering and design (01-08-2012)“…The nuclear engineering infrastructure of port-based diagnostics on ITER is presented, including the equatorial and upper port plug generic designs, the…”
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16
Process and overview of diagnostics integration in ITER ports
Published in Fusion engineering and design (01-10-2013)“…► An overview of the Port Integration hardware for tenant system hosting inside ITER diagnostics ports is given. ► The main challenges for diagnostic port…”
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17
Development of ITER diagnostic window assemblies
Published in Fusion engineering and design (01-10-2013)“…•The concepts chosen for ITER Diagnostic Windows are given.•The description of the main components of the window assemblies is presented.•An overview of the…”
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18
On the theoretical–numerical study of the ITER Upper Port Plug structure hydraulic behaviour under steady state and draining and drying transient conditions
Published in Fusion engineering and design (01-12-2011)“…► UPP TS hydraulic behaviour has been investigated under steady state and D&D transient conditions. ► A thermal–hydraulic system code has been adopted and a…”
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19
Electromagnetic studies of the ITER generic upper port plug
Published in Fusion engineering and design (01-10-2011)“…Electromagnetic analysis of the ITER generic upper port plug was carried out to estimate the most severe load to which the in-vessel components would be…”
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Journal Article Conference Proceeding -
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ITER diagnostics ex-vessel engineering services
Published in Fusion engineering and design (01-10-2013)“…•This paper describes about the ITER diagnostics ex-vessel engineering services.•It describes various diagnostics systems, its location and its…”
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