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Results: 1-16 |
Results: 16
In-vessel tritium retention and removal in ITER-FEAT
Authors: Federici, G Brooks, JN Iseli, M Wu, CH
Citation: G. Federici et al., In-vessel tritium retention and removal in ITER-FEAT, PHYS SCR, T91, 2001, pp. 76-83
The effect of detachment on carbon divertor erosion/redeposit ion in the DIII-D tokamak
Authors: Whyte, DG West, WP Wong, CPC Bastasz, R Brooks, JN Wampler, WR Brooks, NH Davis, JW Doerner, RP Haasz, AA Isler, RC Jackson, GL Macaulay-Newcombe, RG Wade, MR
Citation: Dg. Whyte et al., The effect of detachment on carbon divertor erosion/redeposit ion in the DIII-D tokamak, NUCL FUSION, 41(9), 2001, pp. 1243-1252
Investigation of carbon chemical erosion with increasing plasma flux and density
Authors: Whyte, DG Tynan, GR Doerner, RP Brooks, JN
Citation: Dg. Whyte et al., Investigation of carbon chemical erosion with increasing plasma flux and density, NUCL FUSION, 41(1), 2001, pp. 47-62
Erosion/redeposition analysis of lithium-based liquid surface diverters
Authors: Brooks, JN Rognlien, TD Ruzic, DN Allain, JP
Citation: Jn. Brooks et al., Erosion/redeposition analysis of lithium-based liquid surface diverters, J NUCL MAT, 290, 2001, pp. 185-190
Assessment of erosion and tritium codeposition in ITER-FEAT
Authors: Federici, G Brooks, JN Coster, DP Janeschitz, G Kukuskhin, A Loarte, A Pacher, HD Stober, J Wu, CH
Citation: G. Federici et al., Assessment of erosion and tritium codeposition in ITER-FEAT, J NUCL MAT, 290, 2001, pp. 260-265
Combined sheath and thermal analysis of overheated surfaces in fusion devices
Authors: Naujoks, D Brooks, JN
Citation: D. Naujoks et Jn. Brooks, Combined sheath and thermal analysis of overheated surfaces in fusion devices, J NUCL MAT, 290, 2001, pp. 1123-1127
Sheath superheat transmission due to redeposition of thermally emitted material
Authors: Brooks, JN Naujoks, D
Citation: Jn. Brooks et D. Naujoks, Sheath superheat transmission due to redeposition of thermally emitted material, PHYS PLASMA, 7(6), 2000, pp. 2565-2570
A hydrocarbon reaction model for low temperature hydrogen plasmas and an application to the Joint European Torus
Authors: Alman, DA Ruzic, DN Brooks, JN
Citation: Da. Alman et al., A hydrocarbon reaction model for low temperature hydrogen plasmas and an application to the Joint European Torus, PHYS PLASMA, 7(5), 2000, pp. 1421-1432
ALPS - advanced limiter-divertor plasma-facing systems
Authors: Mattas, RF Allain, JP Bastasz, R Brooks, JN Evans, T Hassanein, A Luckhardt, S McCarthy, K Mioduszewski, P Maingi, R Mogahed, E Moir, R Molokov, S Morely, N Nygren, R Rognlien, T Reed, C Ruzic, D Sviatoslavsky, I Sze, D Tillack, M Ulrickson, M Wade, PM Wooley, R Wong, C
Citation: Rf. Mattas et al., ALPS - advanced limiter-divertor plasma-facing systems, FUSION ENG, 49, 2000, pp. 127-134
Modelling and analysis of DIII-D/DiMES sputtered impurity transport experiments
Authors: Brooks, JN Whyte, DG
Citation: Jn. Brooks et Dg. Whyte, Modelling and analysis of DIII-D/DiMES sputtered impurity transport experiments, NUCL FUSION, 39(4), 1999, pp. 525-538
Radiative divertor and scrape-off layer experiments in open and baffled diverters on DIII-D
Authors: Allen, SL Brooks, NH Bastasz, R Boedo, J Brooks, JN Cuthbertson, JW Evans, TE Fenstermacher, ME Hill, DN Hillis, DL Hogan, J Hyatt, AW Isler, RC Jackson, GL Jernigan, T Lasnier, CJ Lehmer, R Leonard, AW Mahdavi, MA Maingi, R Meyer, WH Mioduszewski, PK Moyer, RA Nilson, DG Owen, LW Petrie, TW Porter, GD Rensink, ME Schaffer, MJ Smith, J Staebler, GM Stambaugh, RD Thomas, DM Wade, MR Wampler, WR Watkins, JG West, WP Whyte, DG Wolf, N Wong, CPC Wood, RD
Citation: Sl. Allen et al., Radiative divertor and scrape-off layer experiments in open and baffled diverters on DIII-D, NUCL FUSION, 39(11Y), 1999, pp. 2015-2023
In-vessel tritium retention and removal in ITER
Authors: Federici, G Anderl, RA Andrew, P Brooks, JN Causey, RA Coad, JP Cowgill, D Doerner, RP Haasz, AA Janeschitz, G Jacob, W Longhurst, GR Nygren, R Peacock, A Pick, MA Philipps, V Roth, J Skinner, CH Wampler, WR
Citation: G. Federici et al., In-vessel tritium retention and removal in ITER, J NUCL MAT, 269, 1999, pp. 14-29
Erosion/redeposition analysis: status of modeling and code validation for semi-detached tokamak edge plasmas
Authors: Brooks, JN Alman, D Federici, G Ruzic, DN Whyte, DG
Citation: Jn. Brooks et al., Erosion/redeposition analysis: status of modeling and code validation for semi-detached tokamak edge plasmas, J NUCL MAT, 269, 1999, pp. 58-66
Divertor erosion in DIII-D
Authors: Whyte, DG Bastasz, R Brooks, JN Wampler, WR West, WP Wong, CPC Buzhinskij, OI Opimach, IV
Citation: Dg. Whyte et al., Divertor erosion in DIII-D, J NUCL MAT, 269, 1999, pp. 67-74
Modeling of tritium retention in TFTR
Authors: Skinner, CH Hogan, JT Brooks, JN Blanchard, W Budny, RV Hosea, J Mueller, D Nagy, A Stotler, DP
Citation: Ch. Skinner et al., Modeling of tritium retention in TFTR, J NUCL MAT, 269, 1999, pp. 940-946
US assessment of Advanced Limiter-divertor Plasma-facing Systems (ALPS) - Design, analysis, and R & D needs
Authors: Mattas, RF Bastasz, R Brooks, JN Hassanein, A Luckhardt, S McCarthy, K Mioduszewski, P Mogahed, E Moir, R Morely, N Nygren, R Reed, C Ruzic, D Sviatoslavsky, I Sze, D Tillack, M Wade, PM Wilson, K Wooley, R Wong, C
Citation: Rf. Mattas et al., US assessment of Advanced Limiter-divertor Plasma-facing Systems (ALPS) - Design, analysis, and R & D needs, FUSION TECH, 34(3), 1998, pp. 345-350
Risultati: 1-16 |