Search Results - "PITCHER, C. S"

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  1. 1

    On the theoretical–numerical study of the ITER Upper Port Plug structure hydraulic behaviour under steady state and draining and drying transient conditions by Di Maio, P.A., Paradiso, D., Dell’Orco, G., Pitcher, C.S., Kalish, M.

    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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    Journal Article
  2. 2

    Electromagnetic studies of the ITER generic upper port plug by Sato, K., Yaguchi, E., Pitcher, C.S., Walker, C., Encheva, A., Kawano, Y., Kusama, Y.

    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
  3. 3

    Plasma profiles and flows in the high-field side scrape-off layer in Alcator C-Mod by Smick, N., LaBombard, B., Pitcher, C.S.

    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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    Journal Article
  4. 4

    OSM-EIRENE modeling of neutral pressures in the Alcator C-Mod divertor by Lisgo, S., Börner, P., Boswell, C., Elder, D., LaBombard, B., Lipschultz, B., Pitcher, C.S., Reiter, D., Stangeby, P.C., Terry, J.L., Wiesen, S.

    Published in Journal of nuclear materials (01-03-2005)
    “…The ITER divertor will be more collisional than divertors in existing tokamaks and the neutral modeling tools used for predictive ITER modeling need to be…”
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    Journal Article
  5. 5

    Monte Carlo radiation shielding and activation analyses for the Diagnostic Equatorial Port Plug in ITER by Serikov, A., Fischer, U., Leichtle, D., Pitcher, C.S.

    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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    Journal Article
  6. 6

    ITER hot Cell—Remote handling system maintenance overview by Friconneau, J-P, Beaudoin, V., Dammann, A, Dremel, C., Martins, JP, Pitcher, C.S.

    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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    Journal Article
  7. 7

    Electromagnetic analysis of ITER diagnostic equatorial port plugs during plasma disruptions by Zhai, Y., Feder, R., Brooks, A., Ulrickson, M., Pitcher, C.S., Loesser, G.D.

    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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    Journal Article
  8. 8

    Neutronics for equatorial and upper ports in ITER by Serikov, A., Fischer, U., Henderson, M., Leichtle, D., Pitcher, C.S., Spaeh, P., Strauss, D., Suarez, A., Weinhorst, B.

    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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    Journal Article
  9. 9

    Integration of remote refurbishment performed on ITER components by Dammann, A., Antola, L., Beaudoin, V., Dremel, C., Evrard, D., Friconneau, J.P., Lemée, A., Levesy, B., Pitcher, C.S.

    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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    Journal Article
  10. 10

    Molybdenum erosion measurements in Alcator C-Mod by Wampler, W.R, LaBombard, B, Lipschultz, B, McCracken, G.M, Pappas, D.A, Pitcher, C.S

    Published in Journal of nuclear materials (01-03-1999)
    “…Erosion of molybdenum was measured on a set of 21 tiles after a run campaign of 1090 shots in the Alcator C-Mod tokamak. The net erosion of molybdenum was…”
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    Journal Article
  11. 11

    The remote handling compatibility analysis of the ITER generic upper port plug structure by Ronden, D.M.S., Dammann, A., Elzendoorn, B., Giacomin, T., Heemskerk, C., Loesser, D., Maquet, P., van Oosterhout, J., Pak, S., Pitcher, C.S., Portales, M., Proust, M., Udintsev, V.S., Walsh, M.J.

    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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    Journal Article
  12. 12

    Nuclear engineering of diagnostic port plugs on ITER by Pitcher, C.S., Barnsley, R., Feder, R., Hu, Q., Loesser, G.D., Lyublin, B., Padasalagi, S., Pak, S., Reichle, R., Sato, K., Udintsev, V.S., Walker, C., Walsh, M., Zhai, Y.

    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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    Journal Article
  13. 13

    Development of ITER diagnostic window assemblies by Maquet, Ph, Walker, C.I., Barnsley, R., Bertalot, L., Encheva, A., Pitcher, C.S., Reichle, R., Vayakis, G., Veshchev, E., Udintsev, V.S., Walsh, M.J., Watts, C., Patel, K.M., Giacomin, T., Hughes, Shaun, Taylor, Neill, Pearce, Robert, Okayama, Katsumi

    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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    Journal Article
  14. 14

    Support structure concept for integration of ITER diagnostics in the port cell by Udintsev, V.S., Portalès, M., Giacomin, T., Darcourt, O., Direz, M.-F., Martins, J.P., Penot, C., Arumugam, A.P., Drevon, J.-M., Friconneau, J.P., Levesy, B., Maquet, P., Patel, K.M., Pitcher, C.S., Popova, E., Proust, M., Ronden, D.M.S., Walker, C.I., Walsh, M.J., Watts, C.

    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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    Journal Article
  15. 15

    Plasma boundary and first-wall diagnostics in ITER by Pitcher, C.S., Andrew, P., Barnsley, R., Bertalot, L., Counsell, G.G., Encheva, A., Feder, R.E., Hatae, T., Johnson, D.W., Kim, J., Kusama, Y., Lee, H.G., Mukhin, E.E., Reichle, R., Thomas, D.M., Tugarinov, S.N., Udintsev, V.S., Vasu, P., Vayakis, G., Walker, C.I., Walsh, M.J., Yang, Q.W., Yatsuka, E., Zhao, J., Zvonkov, A.V.

    Published in Journal of nuclear materials (01-08-2011)
    “…ITER plasma boundary and first-wall diagnostics are summarized in terms of their physical implementation and physics motivation. The challenge of extracting…”
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    Journal Article
  16. 16

    Numerical simulation on bake-out of the ITER diagnostic upper port plug by Pak, S., Pitcher, C.S., Kalish, M.R., Cheon, M.S., Seon, C.R., Lee, H.G.

    Published in Fusion engineering and design (01-12-2010)
    “…The diagnostic upper port plug in ITER is fixed to the upper port of the vacuum vessel as a cantilevered beam with bolts and forms a primary vacuum boundary…”
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    Journal Article Conference Proceeding
  17. 17
  18. 18

    2D modelling of the ASDEX-Upgrade scrape-off layer and divertor plasma by Bosch, H.-S., Neuhauser, J., Schneider, R., Field, A., Herrmann, A., Lieder, G., Junker, W., Pitcher, C.S., Reiter, D., Braams, B., ASDEX-Upgrade, Team

    Published in Journal of nuclear materials (01-04-1995)
    “…Due to the open field lines, the scrape-off layer and divertor region of tokamak plasmas is a complex, two-dimensional system, involving transport parallel and…”
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    Journal Article
  19. 19

    The effect of density on divertor conditions in ASDEX-Upgrade by Pitcher, C.S., Bosch, H.-S., Büchl, K., Field, A., Fuchs, C., Haas, G., Junker, W., Neu, R., Neuhauser, J., Wenzel, U., ASDEX-Upgrade Team

    Published in Journal of nuclear materials (01-04-1995)
    “…Detailed experimental divertor data are presented on the profiles of density and temperature in the inner and outer divertor fans, the radiated power…”
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    Journal Article
  20. 20

    Visible imaging of turbulence in the SOL of the Alcator C-Mod tokamak by Terry, J.L., Maqueda, R., Pitcher, C.S., Zweben, S.J., LaBombard, B., Marmar, E.S., Pigarov, A.Yu, Wurden, G.

    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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    Journal Article