cmuxe

 

CMUXE Member Publications

b Jeffrey N. Brooks
Research Professor of Nuclear Engineering
Tel:  765-496-3630: Fax: 765-494-9570
E mail: brooksjn@purdue.edu

  1. Brooks, J.N., El-Guebaly, L., Hassanein, A., and Sizyuk, T. (2015)
    "Plasma-facing material alternatives to tungsten", Nuclear Fusion, 55, 043002 link

  2. Brooks J.N., Hassanein A., Koniges A., Krstic P.S., Rognlien T.D., Sizyuk T., Sizyuk V., and Stotler D.P. (2014), "Scientific and Computational Challenges in Coupled Plasma Edge/Plasma-Material Interactions for Fusion Tokamaks", Contrib. Plasma Phys. 54, 329 link

  3. Rudakov D. L., P. C. Stangeby, W. R. Wampler, J. N. Brooks, N. H. Brooks, J. D. Elder, A. Hassanein, A.W. Leonard, A. G. McLean, R. A. Moyer, T. Sizyuk, J. G. Watkins and C. P. C. Wong (2014), "Net versus gross erosion of high-Z materials in the divertor of DIII-D", Physica Scripta, T159, 014030 link

  4. Brooks J. N., Hassanein A. and Sizyuk T. (2013) “Advanced simulation of mixed-material erosion/evolution and application to low and high-Z containing plasma facing components”
    Journal of Nuclear Materials DOI: 10.1016/j.jnucmat.2013.01.142

  5. Stangeby P.C., Rudakov D. L., Wampler W. R., Brooks J. N., Brooks N. H., Buchenauer D. A., Eldera J. D., Hassanein A., Leonard A. W., McLean A. G., Okamoto A., Sizyuk T., Watkins J.G. and Wonge C.P.C. (2013) “An experimental comparison of gross and net erosion of Mo in the DIII-D divertor”.
    Journal of Nuclear Materials DOI: 10.1016/j.jnucmat.2013.01.052

  6. Brooks J. N. (2013), Analysis of tungsten migration from the C-MOD divertor; prediction of high redeposition rate, and code validation progress
    Nuclear Fusion 53 Art. No. 042001

  7. Brooks J.N., Hassanein A., Sizyuk T. and Allain J. P. (2012)
    "Modeling of plasma/lithium-surface interactions in NSTX: Status and key issues"
    Fusion Engineering Design  87 1737-1740

  8. Brooks J. N, Allain J. P., Whyte D. G., Ochoukov R., Lipschultz B. (2011) 
    "Analysis of C-MOD molybdenum divertor erosion and code/data comparison" 
     Journal of Nuclear Materials 415 S112-S116

  9. Allain J. P., and Brooks J. N. (2011)
    "Lithium surface-response modelling for the NSTX liquid lithium divertor" 
     Nuclear Fusion 51   Art. No. 023002

  10. Brooks, J. N., Allain, J. P., Doerner, R., et al. (2009) "Plasma–surface interaction issues of an all-metal ITER" Nuclear Fusion 49, 035007.

  11. Brooks, J. N., and Allain, J. P. (2008) "Particle deposition and optical response of ITER motional Stark euect diagnostic first mirrors" Nuclear Fusion 48, 045003.

  12. Wong, C. P. C., Rudakov, D. L., Allain, J. P., et al. (2007) "Divertor and midplane materials evaluation system in DIII-D" Journal of Nuclear Materials 363, 276-281.

  13. Rognlien, T. D., Bulmer, R. H., Rensink, M. E., and Brooks, J. N. (2007) "Scrape-off layer plasmas for ITER with 2nd X-point and convective transport effects" Journal of Nuclear Materials 363, 658.

  14. Brooks, J. N., Allain, J. P., and Rognlien, T. D. (2006) "Erosion/redeposition analysis of the ITER first wall with convective and non-convective plasma transport" Physics of Plasmas 13, 122502.

  15. Finken, K. H., Reiter, D., Denner, T., et al. (2005) "The toroidal pump limiter ALT-II in TEXTOR" Fusion Science and Technology 47, 126-137.

  16. Brooks, J. N., Allain, J. P., Rognlien, T. D., and Maingi, R. (2005) "PSI modeling of liquid lithium divertors for the NSTX tokamak" Journal of Nuclear Materials 337, 1053-1057.

  17. Brooks, J. N., Allain, J. P., Bastasz, R., et al. (2005) "Overview of the ALPS program"
     Fusion Science and Technology 47, 669-677.

  18. Brooks, J. N., Allain, J. P., Alman, D. A., and Ruzic, D. N. (2005) "Erosion, transport, and tritium codeposition analysis of a beryllium wall tokamak" Fusion Engineering and Design 72, 363-375.

  19. Allain, J. P., Brooks, J. N., Alman, D. A., and Gonzalez, L. E. (2005) "Model development and analysis of temperature-dependent lithium sputtering and sputtered Li+ transport for tokamak plasma-facing applications" Journal of Nuclear Materials 337, 94-98.

  20. Whyte, D. G., Evans, T. E., Wong, C. P. C., et al. (2004) "Experimental observations of lithium as a plasma-facing surface in the DIII-D tokamak divertor" Fusion Engineering & Design 72, 133-147.

  21. Whyte, D. G., Brooks, J. N., Stangeby, P. C., and Brooks, N. H. (2004) "A detailed study of carbon chemical erosion in L-mode plasmas in the DIII-D divertor" Physica Scripta T111, 34-41.

  22. Hassanein, A., Burtseva, T., Brooks, J. N., Konkashbaev, I., and Rice, B. (2004)
    "Candidate plasma-facing materials for extreme ultraviolet lithography source components" Journal of Microlithography Microfabrication and Microsystems 3, 529-536.

  23. Allain, J. P., Whyte, D. G., and Brooks, J. N. (2004) "Lithium erosion experiments and modelling under quiescent plasma conditions in DIII-D" Nuclear Fusion 44, 655-664.

  24. Kirschner, A., Brooks, J. N., Philipps, V., et al. (2003) "Modelling of the transport of methane and higher hydrocarbons in fusion devices" Journal of Nuclear Materials 313, 01355-7.

  25. Kirschner, A., Brooks, J. N. et al. (2003) "Hydrocarbon transport in the MkIIa divertor of JET" Plasma Physics and Controlled Fusion 45, PII S0741-3335(03)37188-X.

  26. Brooks, J. N., Kirschner, A., Whyte, D. G., Ruzic, D. N., and Alman, D. A. (2003) "Advances in the modeling of chemical erosion/redeposition of carbon divertors and application to the JET tritium codeposition problem" Journal of Nuclear Materials 313, PII S0022-3115(02)01405-8.

  27. Causey, R. A., Brooks, J. N., and Federici, G. (2002) "Tritium inventory and recovery in next-step fusion devices" Fusion Engineering and Design 61-2, PII S0920-3796(02)00248-X.

  28. Brooks, J. N. (2002) "Modeling of sputtering erosion/redeposition - status and implications for fusion design" Fusion Engineering and Design 60, PII S0920-3796(02)00007-8.

  29. Alman, D. A., Ruzic, D. N., and Brooks, J. N. (2002) "A hydrocarbon reaction model for low temperature hydrogen plasmas and an application to the Joint European Torus (vol 7, pg 1421, 2000)" Physics of Plasmas 9, 738-740.

  30. Whyte, D. G., West, W. P., Wong, C. P. C., et al. (2001) "The effect of detachment on carbon divertor erosion/redeposit ion in the DIII-D tokamak" Nuclear Fusion 41, 1243-1252.

  31. Whyte, D. G., Tynan, G. R., Doerner, R. P., and Brooks, J. N. (2001) "Investigation of carbon chemical erosion with increasing plasma flux and density" Nuclear Fusion 41, 47-62.

  32. Ulrickson, M. A., Brooks, J. N., Driemeyer, D. E., et al. (2001) "Physics basis for the fusion ignition research experiment plasma facing components" Fusion Engineering and Design 58-9, 907-912.

  33. Naujoks, D., and Brooks, J. N. (2001) "Combined sheath and thermal analysis of overheated surfaces in fusion devices" Journal of Nuclear Materials 290, 1123-1127.

  34. 2Federici, G., Skinner, C. H., Brooks, J. N., et al. (2001) "Plasma-material interactions in current tokamaks and their implications for next step fusion reactors" Nuclear Fusion 41, 1967-2137.

  35. Federici, G., Brooks, J. N., Iseli, M., and Wu, C. H. (2001) "In-vessel tritium retention and removal in ITER-FEAT" Physica Scripta T91, 76-83.

  36. Federici, G., Brooks, J. N., Coster, D. P., et al. (2001) "Assessment of erosion and tritium codeposition in ITER-FEAT" Journal of Nuclear Materials 290, 260-265.

  37. Brooks, J. N., Rognlien, T. D., Ruzic, D. N., and Allain, J. P. (2001) "Erosion/redeposition analysis of lithium-based liquid surface diverters" Journal of Nuclear Materials 290, 185-190.

  38. Mattas, R. F., Allain, J. P., Bastasz, R., et al. (2000) "ALPS - advanced limiter-divertor plasma-facing systems" Fusion Engineering and Design 49, 127-134.

  39. Brooks, J. N., and Naujoks, D. (2000) "Sheath superheat transmission due to redeposition of thermally emitted material" Physics of Plasmas 7, 2565-2570.

  40. Alman, D. A., Ruzic, D. N., and Brooks, J. N. (2000) "A hydrocarbon reaction model for low temperature hydrogen plasmas and an application to the Joint European Torus"
    Physics of Plasmas 7, 1421-1432.

  41. Whyte, D. G., Bastasz, R., Brooks, J. N., et al. (1999) "Divertor erosion in DIII-D" Journal of Nuclear Materials 266, 67-74.

  42. Skinner, C. H., Hogan, J. T., Brooks, J. N., et al. (1999) "Modeling of tritium retention in TFTR" Journal of Nuclear Materials 266, 940-946.

  43. Federici, G., Anderl, R. A., Andrew, P., et al. (1999) "In-vessel tritium retention and removal in ITER" Journal of Nuclear Materials 266, 14-29.

  44. Brooks, J. N., and Whyte, D. G. (1999) "Modelling and analysis of DIII-D/DiMES sputtered impurity transport experiments" Nuclear Fusion 39, 525-538.

  45. Brooks, J. N., Alman, D., Federici, G., Ruzic, D. N., and Whyte, D. G. (1999) "Erosion/redeposition analysis: status of modeling and code validation for semi-detached tokamak edge plasmas" Journal of Nuclear Materials 266, 58-66.

  46. Allen, S. L., Brooks, N. H., Bastasz, R., et al. (1999) "Radiative divertor and scrape-off layer experiments in open and baffled diverters on DIII-D" Nuclear Fusion 39, 2015-2023.

  47. Mattas, R. F., Bastasz, R., Brooks, J. N., et al. (1998) "US assessment of Advanced Limiter-divertor Plasma-facing Systems (ALPS) - Design, analysis, and R & D needs" Fusion Technology 34, 345.

  48. Federici, G., Anderl, R., Brooks, J. N., et al. (1998) "Tritium inventory in the ITER PFC's: Predictions, uncertainties, R & D status and priority needs" Fusion Engineering and Design 39-4, 445-464.

  49. Whyte, D. G., Brooks, J. N., Wong, C. P. C., et al. (1997) "DiMES divertor erosion experiments on DIII-D" Journal of Nuclear Materials 241, 660-665.

  50. Brooks, J. N., Ruzic, D. N., and Hayden, D. B. (1997) "Sputtering erosion of beryllium coated plasma facing components - general considerations and analysis for ITER detached plasma regime" Fusion Engineering and Design 37, 455-463.

  51. Brooks, J. N., Causey, R., Federici, G., and Ruzic, D. N. (1997) "Assessment of erosion and surface tritium inventory issues for the ITER divertor" Journal of Nuclear Materials 241, 294-298.

  52. Brooks, J. N. (1996) "Analysis of noble gas recycling at a fusion plasma divertor" Physics of Plasmas 3, 2286-2292.

  53. Boivin, R., Brooks, J. N., Khandagle, M. J., Hirooka, Y., and Won, J. (1996) "Plasma sputtered Mo impurity transport experiment in PISCES-B Mod; Assessment of atomic process rate coefficients and redeposition characteristics" Journal of Nuclear Materials 230, 101-109

  54. Hua, T. Q., and Brooks, J. N. (1995) "EROSION REDEPOSITION ANALYSIS OF THE DIII-D DIVERTOR" Journal of Nuclear Materials 220, 342-346.

  55. Hill, D. N., Braams, B., Brooks, J. N., et al. (1995) "DIVERTOR DESIGN FOR THE TOKAMAK PHYSICS EXPERIMENT" Journal of Nuclear Materials 220, 698-702.

  56. Brooks, J. N., Ruzic, D. N., Hayden, D. B., and Turkot, R. B. (1995) "SURFACE EROSION ISSUES AND ANALYSIS FOR DISSIPATIVE DIVERTORS" Journal of Nuclear Materials 220, 269-273.

  57. Hua, T. Q., and Brooks, J. N. (1994) "ANALYSIS OF THE TOKAMAK SHEATH REGION WITH IN-SHEATH IONIZATION AND TRANSPORT OF SURFACE EMITTED PARTICLES"
    Physics of Plasmas 1, 3607-3613.

  58. Hirooka, Y., Won, J., Keller, S., Boivin, R., Khandagle, M., and Brooks, J. N. (1994) "EVALUATION OF EROSION AND LIFETIME OF ITER DIVERTOR CANDIDATE MATERIALS AND RELEVANT DATA FROM RECENT EXPERIMENTS IN THE PISCES-B MOD FACILITY"
    Fusion Technology 26, 540-545.

  59. Schmidt, J. A., Thomassen, K. I., Goldston, R. J., et al. (1993) "THE DESIGN OF THE TOKAMAK PHYSICS EXPERIMENT (TPX)" Journal of Fusion Energy 12, 221-258.

  60. Khandagle, M. J., Hirooka, Y., Conn, R. W., Brooks, J. N., Hassanein, A., and Turkot, R. B. (1993) "IMPURITY TRANSPORT UNDER STEADY-STATE MAGNETIZED PLASMA BOMBARDMENT IN PISCES-B MOD" Journal of Nuclear Materials 207, 116-122.

  61. Ulrickson, M., Goldston, R., Brooks, J. N., et al. (1992) "A TRITIUM INVENTORY MANAGEMENT SCHEME FOR BPX" 14th Ieee / Npss Symposium : Fusion Engineering, Proceedings, Vols 1 and 2, 1008-1011.

  62. Ulrickson, M., Brooks, J. N., Dylla, H. F., et al. (1992) "IMPURITY CONTROL AND MATERIALS PHYSICS" Fusion Technology 21, 1279-1291.

  63. Nygren, R. E., Doyle, B. L., Walsh, D. S., Ottenberger, W., Brooks, J. N., and Krauss, A. (1992) "LOW-ENERGY HELIUM IMPLANTATION IN EVAPORATED NICKEL SURFACES"
    Journal of Nuclear Materials 196, 558-563.

  64. Hua, T. Q., and Brooks, J. N. (1992) "ANALYSIS OF EROSION AND TRANSPORT OF CARBON IMPURITY IN THE TFTR INNER BUMPER LIMITER REGION"
    Journal of Nuclear Materials 196, 514-519.

  65. Hirooka, Y., Bourham, M., Brooks, J. N., et al. (1992) "EVALUATION OF TUNGSTEN AS A PLASMA-FACING MATERIAL FOR STEADY-STATE MAGNETIC FUSION DEVICES"
    Journal of Nuclear Materials 196, 149-158.

  66. Brooks, J. N., Krauss, A., Nygren, R. E., Doyle, B. L., Dippel, K. H., and Finken, K. H. (1992) "SUMMARY OF RESULTS FROM THE TEXTOR HELIUM SELF-PUMPING EXPERIMENT" Journal of Nuclear Materials 196, 664-669.

  67. Brooks, J. N., and Ruzic, D. N. (1990) "MODELING AND ANALYSIS OF SURFACE-ROUGHNESS EFFECTS ON SPUTTERING, REFLECTION AND SPUTTERED PARTICLE-TRANSPORT" Journal of Nuclear Materials 176, 278-282.

  68. Brooks, J. N., Nygren, R. E., Dippel, K. H., et al. (1990) "THE TEXTOR HELIUM SELF-PUMPING EXPERIMENT - DESIGN, PLANS, AND SUPPORTING ION-BEAM DATA ON HELIUM RETENTION IN NICKEL" Journal of Nuclear Materials 176, 635-639.

  69. Brooks, J. N. (1990) "NEAR-SURFACE SPUTTERED PARTICLE-TRANSPORT FOR AN OBLIQUE-INCIDENCE MAGNETIC-FIELD PLASMA" Physics of Fluids B-Plasma Physics 2, 1858-1863.

  70. Brooks, J. N. (1990) "EROSION REDEPOSITION ANALYSIS OF THE INTERNATIONAL THERMONUCLEAR EXPERIMENTAL REACTOR DIVERTOR" Fusion Technology 18, 239-250.

  71. Brooks, J. N. (1990) "TEMPERATURE LIMIT OF A GRAPHITE DIVERTOR SURFACE DUE TO SELF-SPUTTERING AND RADIATION ENHANCED SUBLIMATION"
    Journal of Nuclear Materials 170, 164-168.

  72. Pontau, A. E., Brice, D. K., Buchenauer, D. A., et al. (1989) "TFTR TRITIUM INVENTORY ANALYSIS" Fusion Engineering and Design 10, 365-371.

  73. McGrath, R. T., Brooks, J. N. (1989) "TRANSPORT OF SPUTTERED IMPURITIES IN THE VICINITY OF THE TFTR INNER BUMPER LIMITER" Journal of Nuclear Materials 162, 350-355.

  74. Brooks, J. N., Brice, D. K., Dewald, A. B., and McGrath, R. T. (1989) "EROSION REDEPOSITION MODELING AND CALCULATIONS FOR CARBON" Journal of Nuclear Materials 162, 363-368.

  75. Brooks, J. N., et al. (1988) "IMPURITY TRANSPORT CALCULATIONS FOR A DRIFT-DEPENDENT TOKAMAK SCRAPE-OFF PLASMA" Contributions to Plasma Physics 28, 465-470.

  76. McGrath, R. T., Doyle, B. L., Brooks, J. N., Pontau, A. E., and Thomas, G. J. (1987) "IMPURITY DEPOSITION ON ALT-I LIMITER HEADS" Journal of Nuclear Materials 145, 660-664.

  77. Dewald, A. B., Brooks, J. N., Krauss, A. R., Gruen, D. M., and Valentine, M. G. (1987) "A SPUTTERING REDEPOSITION ANALYSIS OF ALKALI-BASED TUNGSTEN COMPOSITES FOR LIMITER DIVERTOR APPLICATIONS" Journal of Nuclear Materials 145, 373-378.

  78. Dewald, A. B., Brooks, J. N., Krauss, A. R., and Gruen, D. M. (1987) "THE SPUTTERING AND REDEPOSITION BEHAVIOR OF VBE12 COMPOUND AND OF TI-CU-LI COMPOSITES WITHIN A FUSION TOKAMAK ENVIRONMENT"
    Journal of Vacuum Science & Technology a-Vacuum Surfaces and Films 5, 2763-2767.

  79. Dewald, A. B., Bailey, A. W., and Brooks, J. N. (1987) "TRAJECTORIES OF CHARGED-PARTICLES TRAVERSING A PLASMA SHEATH IN AN OBLIQUE B-FIELD" Physics of Fluids 30, 267-269.

  80. Brooks, J. N. (1987) "TWO-DIMENSIONAL IMPURITY TRANSPORT CALCULATIONS FOR A HIGH RECYCLING DIVERTOR" Journal of Nuclear Materials 145, 837-840.

  81. Mattas, R. F., Baskes, M. I., Brooks, J. N., Blanchard, J. P., Hassanein, A. M., and Tobin, A. (1986) "DIVERTOR ENGINEERING STUDIES FOR THE INTERNATIONAL TOKAMAK REACTOR" Fusion Technology 10, 364-381.

  82. Krauss, A. R., Gruen, D. M., Brooks, J. N., and Dewald, A. B. (1986) "COMPOSITE-MATERIALS FOR HIGH HEAT AND PARTICLE-FLUX COMPONENTS IN FUSION DEVICES"
    Journal of Vacuum Science & Technology a-Vacuum Surfaces and Films 4, 1227-1231.

  83. Finn, P. A., Brooks, J. N., Ehst, D. A., Gohar, Y., Mattas, R. F., and Baker, C. C. (1986) "AN EVALUATION OF POLARIZED FUELS IN A COMMERCIAL DEUTERIUM TRITIUM TOKAMAK REACTOR" Fusion Technology 10, 902-907.

  84. Brooks, J. N. (1986) "SPUTTERING PERFORMANCE OF A PUMPED LIMITER FOR AN IGNITION TOKAMAK" Fusion Technology 9, 340-344.

  85. Baker, C. C., Ehst, D. A., Brooks, J. N., and Evans, K. (1986) "TOKAMAK POWER-SYSTEMS STUDIES AT ANL" Fusion Technology 10, 709-716.

  86. Terry, W. K., Brooks, J. N., and Boley, C. D. (1985) "TRANSPORT CODE ANALYSIS OF SOME ASPECTS OF IMPURITY CONTROL IN REACTOR GRADE TOKAMAK PLASMAS"
    Fusion Technology 7, 158-170.

  87. Krauss, A. R., Gruen, D. M., Brooks, J. N., Mendelsohn, M. H., Mattas, R. F., and Dewald, A. B. (1985) "SELF-SUSTAINING COATINGS FOR FUSION APPLICATIONS - COPPER LITHIUM ALLOYS" Fusion Technology 8, 1269-1274.

  88. Ehst, D. A., Brooks, J. N., Evans, K., and Kim, S. (1985) "A COMPARISON OF PULSED AND STEADY-STATE TOKAMAK REACTOR BURN CYCLES .2. MAGNET FATIGUE, POWER-SUPPLIES, AND COST-ANALYSIS" Nuclear Engineering and Design-Fusion 2, 319-336.

  89. Ehst, D. A., Brooks, J. N., Cha, Y., et al. (1985) "A COMPARISON OF BURN CYCLE OPTIONS FOR TOKAMAK REACTORS" Fusion Technology 8, 727-730.

  90. Brooks, J. N., Mattas, R. F., Ehst, D. A., and Hershkowitz, N. (1985) "AN IMPURITY CONTROL TEST FACILITY (ICTF) FOR THE STUDY OF FUSION-REACTOR PLASMA EDGE MATERIALS" Fusion Technology 8, 1766-1771.

  91. Brooks, J. N., Gruen, D. M., Krauss, A. R., Mattas, R. F., and Dewald, A. B. (1985) "CURRENT STATE OF DEVELOPMENT AND EXPECTED PERFORMANCE OF COPPER-LITHIUM ALLOYS AS AN IMPURITY CONTROL-SYSTEM IN FUSION APPLICATIONS"
    Fusion Technology 8, 1275-1280.

  92. Baker, C. C., Brooks, J. N., Ehst, D. A., Smith, D. L., and Sze, D. K. (1985) "STARFIRE-II STUDIES" Transactions of the American Nuclear Society 49, 124-125.

  93. Brooks, J. N., Mattas, et al.. (1984) "DESIGN AND ANALYSIS OF A LOW-EDGE-TEMPERATURE DIVERTOR FOR INTOR" Journal of Nuclear Materials 128, 400-406.

  94. Brooks, J. N., and Mattas, R. F. (1984) "SELF-PUMPING IMPURITY CONTROL BY INSITU METAL-DEPOSITION" Journal of Nuclear Materials 121, 392-397.

  95. Brooks, J. N., and Kaminsky, M. (1984) "INFLUENCE OF EROSION AND REDEPOSITION PROCESSES ON THE LIFETIME OF IMPURITY CONTROL COMPONENTS - AN ASSESSMENT FOR TIC COATINGS" Fusion Technology 6, 465-474.

  96. Evans, K., Baker, C. C., Brooks, J. N., et al. (1983) "WILDCAT - A COMMERCIAL DEUTERIUM-DEUTERIUM TOKAMAK REACTOR" Nuclear Technology-Fusion 4, 226-252.

  97. Brooks, J. N. (1983) "MODELING AND ANALYSIS OF EROSION AND REDEPOSITION FOR LIMITER AND DIVERTOR IMPURITY CONTROL-SYSTEMS" Nuclear Technology-Fusion 4, 33.

  98. Brooks, J. N. (1982) "EROSION AND REDEPOSITION ANALYSIS FOR LIMITER AND DIVERTOR IMPURITY CONTROL-SYSTEMS" Journal of Nuclear Materials 111, 457-458.

  99. Gohar, Y., and Brooks, J. N. (1981) "1ST WALL HEAT LOAD IN THE STARFIRE COMMERCIAL TOKAMAK REACTOR" Transactions of the American Nuclear Society 38, 232-233.

  100. Baker, C. C., Abdou, M. A., Boley, C. D., et al. (1981) "STARFIRE, A COMMERCIAL TOKAMAK POWER-PLANT DESIGN" Nuclear Engineering and Design 63, 199-231.

  101. Schwager, L. A., Brooks, J. N., Boley, C. D., and Gelbard, E. M. (1980) "KINETIC-BEHAVIOR OF A PLASMA NEAR A REACTOR WALL" Bulletin of the American Physical Society 25, 937-937.

  102. Evans, K., Ehst, D. A., and Brooks, J. N. (1980) "PLASMA PHYSICS CONSIDERATIONS OF TOKAMAK REACTORS OPERATING ON DD-FUEL CYCLES"
    Bulletin of the American Physical Society 25, 937-937.

  103. Brooks, J. N., Ehst, D., and Dreimeyer, D. (1980) "BURN CYCLE OF THE STARFIRE TOKAMAK REACTOR" Bulletin of the American Physical Society 25, 937-937.

  104. Brooks, J. N. (1980) "SELF-CONSISTENT CALCULATIONS OF EDGE TEMPERATURE AND SELF-SPUTTERING OF THE LIMITER SURFACE FOR TOKAMAK FUSION-REACTORS" Journal of Nuclear Materials 93-4, 437-441.

  105. Boley, C. D., and Brooks, J. N. (1980) "ONE-DIMENSIONAL PLASMA TRANSPORT RESULTS FOR THE STARFIRE TOKAMAK REACTOR" Bulletin of the American Physical Society 25, 937-937.

  106. Brooks, J. N., and Kustom, R. L. (1979) "POWER-SUPPLY REQUIREMENTS FOR A TOKAMAK FUSION-REACTOR" Nuclear Technology 46, 61-81.

  107. Brooks, J. N. (1979) "STUDY OF THE PLASMA-EDGE REGION IN A TOKAMAK FUSION-REACTOR" Transactions of the American Nuclear Society 32, 74-74.

  108. Olson, J. R., Amme, R. C., Brooks, J. N., et al. (1978) "BALLOON-BORNE ION SAMPLING PACKAGE" Review of Scientific Instruments 49, 643-649.

  109. Brooks, J. N., and Smith, D. L. (1978) "IMPURITY CONTROL IN TOKAMAK FUSION REACTORS BY A HELIUM RETENTION WALL" Bulletin of the American Physical Society 23, 802-802.

  110. Stacey, W. M., Brooks, J. N., and Smith, D. L. (1977) "IMPURITY CONTROL IN TOKAMAK REACTORS" Bulletin of the American Physical Society 22, 1096-1096.

  111. Stacey, W. M., Brooks, J. N., and Smith, D. L. (1977) "MODELING AND ANALYSIS OF IMPURITY CONTROL TECHNIQUES FOR TOKAMAK FUSION REACTORS"
    Transactions of the American Nuclear Society 26, 79-80.

  112. Abdou, M. A., Brooks, et al. (1977) "IMPACT OF MAJOR DESIGN PARAMETERS ON ECONOMICS OF TOKAMAK POWER-PLANTS" Trans American Nuclear Society 26, 46-47.

  113. Stacey, W. M., Maroni, V. A., Purcell, J. R., et al. (1976) "TOKAMAK EXPERIMENTAL POWER-REACTOR" Nuclear Technology 30, 261-298.

  114. Stacey, W. M., Brooks, J. N., and Evans, K. (1976) "PLASMA PHYSICS CONSIDERATIONS FOR A TOKAMAK EXPERIMENTAL POWER-REACTOR" Bul. American Physical Society 21, 1194.

  115. Stacey, W. M., and Brooks, J. N. (1976) "CORE-CORONA MODEL FOR TOKAMAK REACTOR PLASMA SIMULATION" Transactions of the American Nuclear Society 23, 47-47.

  116. Stacey, W. M., Bertoncini, P. J., Brooks, J. N., and Evans, K. (1976) "EFFECT OF PLASMA CONFINEMENT AND IMPURITY LEVEL UPON PERFORMANCE OF A D-T BURNING TOKAMAK EXPERIMENTAL POWER-REACTOR" Nuclear Fusion 16, 211-223.

  117. Stacey, W. M., Maroni, V. A., Purcell, J. R., et al. (1975) "ARGONNE TOKAMAK EXPERIMENTAL POWER-REACTOR STUDIES" Transactions of the American Nuclear Society 22, 61-62.

  118. Stacey, W. M., Evans, K., Bertoncini, P. J., and Brooks, J. N. (1975) "ENGINEERING PLASMA PHYSICS CONSIDERATIONS FOR A TOKAMAK EXPERIMENTAL POWER-REACTOR" Transactions of the American Nuclear Society 21, 32-33.

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