Search Results - "Khater, H.Y."

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  1. 1

    Nuclear features of the fusion ignition research experiment (FIRE) by Sawan, Mohamed E, Khater, H.Y, Zinkle, S.J

    Published in Fusion engineering and design (01-12-2002)
    “…The main nuclear features of the baseline design of fusion ignition research experiment (FIRE) have been evaluated. Critical issues were addressed and R&D…”
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    Journal Article Conference Proceeding
  2. 2

    Nuclear analysis for a flowing Li 2O particulate blanket without structural first wall by Sawan, M.E, Khater, H.Y, Sze, D.-K

    Published in Fusion engineering and design (2000)
    “…Neutronics and activation calculations have been performed for a Li 2O particulate blanket concept without structural first wall. The concept has the potential…”
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    Journal Article
  3. 3

    ARIES-ST safety design and analysis by Khater, H.Y, Mogahed, E.A, Sze, D.K, Tillack, M.S, Wang, X.R

    Published in Fusion engineering and design (01-02-2003)
    “…Activation and safety analyses were performed for the ARIES-ST design. The ARIES-ST power plant includes a water-cooled copper centerpost. The first wall and…”
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    Journal Article
  4. 4

    Safety implications of CLiFF liquid metal first walls by Merrill, B.J, Sze, D.-K, Khater, H.Y, Mogahed, E.A

    Published in Fusion engineering and design (01-12-2002)
    “…In this article we explore some of the safety issues associated with the Advanced Power Extraction (APEX) liquid metal first wall (FW) concept called the…”
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    Journal Article Conference Proceeding
  5. 5

    Activation analysis of the PULSAR-I fusion power reactor by Khater, H.Y.

    “…PULSAR-I is a 1000 MWe pulsed inductively-driven tokamak design. The reactor uses a helium-cooled SiC composite as a structural material and Li/sub 2/O as a…”
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    Conference Proceeding
  6. 6

    Results of the activation analysis of the stellarator power plant study by Khater, H.Y.

    “…Detailed activation analysis is performed as a part of the Stellarator Power Plant Study (SPPS). The reactor is assumed to operate for 30 full power years…”
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    Conference Proceeding
  7. 7

    Activation analysis of the PULSAR-II fusion power reactor by Khater, H.Y.

    “…The PULSAR-II pulsed tokamak power plant design utilizes a blanket made of the vanadium alloy, V-5Cr-5Ti, and cooled with liquid lithium. The shield is made of…”
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    Conference Proceeding
  8. 8
  9. 9

    Activation and waste disposal of the ARIES-II tokamak fusion power reactor by Khater, H.Y.

    “…A detailed activation analysis has been performed for the tokamak fusion power reactor ARIES-II. The reactor uses vanadium alloy as a structural material and…”
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    Conference Proceeding
  10. 10

    Radiological dose calculations for the particle beam fusion accelerator upgrade (PBFA-U) by Khater, H.Y, Sawan, M.E

    Published in Fusion engineering and design (02-03-1995)
    “…Biological dose rate calculations are performed for different locations in the vicinity of the target chamber and diode of the particle beam fusion accelerator…”
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    Journal Article
  11. 11

    Experimental validation of calculations of decay heat induced by 14 MeV neutron activation of ITER materials by Taylor, N.P, Ikeda, Y, Bartels, H.-W, Cambi, G, Cepraga, D.G, Cheng, E.T, Forrest, R.A, Iida, H, Khater, H.Y, Maekawa, F, Saji, G, Santoro, R.T, Sawan, M.E, Sublet, J.-Ch, Youssef, M.Z

    Published in Fusion engineering and design (01-03-1999)
    “…In a D-T fusion tokamak, neutron activation of structural material will result in a source of heat from radioactive decay after shutdown of the plasma…”
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    Journal Article
  12. 12

    Nuclear analysis for the blanket and shield of the KrF laser driven inertial fusion reactor SOMBRERO by Sawan, M.E., Khater, H.Y.

    “…The SOMBRERO inertial fusion reactor conceptual design produces 1000 MWe utilizing near symmetric illumination of targets by KrF laser. The blanket design…”
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    Conference Proceeding
  13. 13

    The importance of using the mixed neutron flux in activation analysis of D-/sup 3/He fueled reactors by Khater, H.Y., Sawan, M.E.

    “…It is emphasized that the mixed neutron source should always be used in any activation and safety analysis performed for D-/sup 3/He reactors. It is noted that…”
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    Conference Proceeding
  14. 14

    Safety and environmental aspects of the Apollo-L2 D-/sup 3/He reactor by Khater, H.Y., Sawan, M.E.

    “…Apollo-L2 is a D-/sup 3/He fueled tokamak reactor design that utilizes direct conversion. The reactor shield is made of steel and cooled with water. Three…”
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    Conference Proceeding
  15. 15

    Activation analysis for the plasma facing component of ITER divertor by Khater, H.Y., Sawan, M.E., Henderson, D.L.

    “…A three-dimensional activation analysis for the divertor of the International Thermonuclear Experimental Reactor (ITER) design has been performed. Results of…”
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    Conference Proceeding
  16. 16

    Profit from borating concrete in the ITER biological shield by Khripunov, V., Santoro, R.T., Khater, H.Y.

    “…Reduction of the radiation doses in the ITER cryostat-biological shield region is important for the ITER maintenance. In this paper, the use of borated…”
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    Conference Proceeding
  17. 17

    ITER shielding analysis by Santoro, R.T, Gohar, Y, Parker, R.R, Shatalov, G, Sawan, M.E, Khater, H.Y

    Published in Fusion engineering and design (01-03-1995)
    “…Radiation transport calculations have been carried out to aid in the design of the reference shielding and breeding blankets proposed for the International…”
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    Journal Article
  18. 18

    Assessment of personnel accessibility in the Particle Beam Fusion Accelerator facility PBFA-II by Sawan, M.E., El-Guebaly, L.A., Khater, H.Y.

    “…The dose during and after fusion shots around the PBFA-II facility and the line-of-sight (LOS) beam penetration has been calculated. The dose above the 6"…”
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    Conference Proceeding
  19. 19

    A complete loss of coolant accident (LOCA) analysis for the inboard component of ITER CDA by Mogahed, E.A., Sawan, M.E., Khater, H.Y.

    “…A two-dimensional thermal transient analysis, r-/spl theta/ model, has been performed to study three cases of total LOCA in the inboard components for the ITER…”
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    Conference Proceeding
  20. 20

    Environmental and safety assessment of the inertially confined direct drive laser fusion power reactor SIRIUS-P by Khater, H.Y., Wittenberg, L.J., Sawan, M.E.

    “…Environmental and safety analyses have been performed for SIRIUS-P, and its target factory and fuel reprocessing facilities. Both the C/C composite chamber and…”
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    Conference Proceeding