Search Results - "Khater, H.Y."
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1
Nuclear features of the fusion ignition research experiment (FIRE)
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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2
Nuclear analysis for a flowing Li 2O particulate blanket without structural first wall
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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3
ARIES-ST safety design and analysis
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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4
Safety implications of CLiFF liquid metal first walls
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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5
Activation analysis of the PULSAR-I fusion power reactor
Published in Proceedings of 16th International Symposium on Fusion Engineering (1995)“…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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6
Results of the activation analysis of the stellarator power plant study
Published in Proceedings of 16th International Symposium on Fusion Engineering (1995)“…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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7
Activation analysis of the PULSAR-II fusion power reactor
Published in Proceedings of 16th International Symposium on Fusion Engineering (1995)“…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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8
Nuclear analysis for a flowing Li2O particulate blanket without structural first wall
Published in Fusion engineering and design (01-11-2000)Get full text
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9
Activation and waste disposal of the ARIES-II tokamak fusion power reactor
Published in 15th IEEE/NPSS Symposium. Fusion Engineering (1993)“…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
Radiological dose calculations for the particle beam fusion accelerator upgrade (PBFA-U)
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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11
Experimental validation of calculations of decay heat induced by 14 MeV neutron activation of ITER materials
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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12
Nuclear analysis for the blanket and shield of the KrF laser driven inertial fusion reactor SOMBRERO
Published in 15th IEEE/NPSS Symposium. Fusion Engineering (1993)“…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
The importance of using the mixed neutron flux in activation analysis of D-/sup 3/He fueled reactors
Published in [Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering (1991)“…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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14
Safety and environmental aspects of the Apollo-L2 D-/sup 3/He reactor
Published in [Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering (1991)“…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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15
Activation analysis for the plasma facing component of ITER divertor
Published in 17th IEEE/NPSS Symposium Fusion Engineering (Cat. No.97CH36131) (1997)“…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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16
Profit from borating concrete in the ITER biological shield
Published in 17th IEEE/NPSS Symposium Fusion Engineering (Cat. No.97CH36131) (1997)“…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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17
ITER shielding analysis
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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18
Assessment of personnel accessibility in the Particle Beam Fusion Accelerator facility PBFA-II
Published in 15th IEEE/NPSS Symposium. Fusion Engineering (1993)“…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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19
A complete loss of coolant accident (LOCA) analysis for the inboard component of ITER CDA
Published in 15th IEEE/NPSS Symposium. Fusion Engineering (1993)“…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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20
Environmental and safety assessment of the inertially confined direct drive laser fusion power reactor SIRIUS-P
Published in 15th IEEE/NPSS Symposium. Fusion Engineering (1993)“…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