Zobrazeno 1 - 10
of 161
pro vyhledávání: '"H.Y. Khater"'
Publikováno v:
Fusion Science and Technology. 44:375-381
This article summarizes the results of the safety evaluation of the Evaporation of Lithium and Vapor Extraction (EVOLVE) W-alloy first wall (FW) and blanket concept'. We have analyzed the EVOLVE design response during a confinement bypass accident. A
Publikováno v:
Fusion Engineering and Design. :547-557
The main nuclear features of the baseline design of fusion ignition research experiment (FIRE) have been evaluated. Critical issues were addressed and R&D needs were identified. Modest values of nuclear heating occur in the FIRE components. The total
Publikováno v:
Fusion Engineering and Design. :285-293
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 Convective Liquid Flow First Wall (CLiFF) design. In particular, we examine the chemical reactiv
Publikováno v:
Fusion Technology. 39:1013-1017
Using xenon as a fill gas in IFE chambers results in generating a large amount of radioactive xenon, iodine, and cesium isotopes. The cesium isotopes, 134 Cs and 136 Cs, and the iodine isotope, 126 I, would produce a high level of off-site dose (62.1
Publikováno v:
Fusion Technology. 39:804-809
Plasma stabilization and plasma elongation are best achieved by keeping a stabilizing shell as close as possible to the plasma. In CLiFF design, a 2-cm-thick flowing liquid layer is placed in front of a solid FW and is thought to be used as an active
Publikováno v:
Fusion Technology. 39:1003-1007
Hands-on maintenance activities outside the X-1 aluminum chamber may be allowed within a few hours following radiation (photoneutron) shots. Dose rates outside the chamber following moderate yield (200 MJ) shots are four orders of magnitude higher th
Publikováno v:
Fusion Technology. 39:639-643
A tritium-breeding blanket design is investigated for a D-T Field-Reversed Configuration (FRC) scoping study. The thrust of our initial effort on the blanket has been to seek solutions as close to present-day technology as possible, and we have there
Autor:
Mohamed E. Sawan, H.Y. Khater
Publikováno v:
Fusion Technology. 39:393-397
Neutronics and activation calculations have been performed for the FIRE design with different first wall design options. Modest values of nuclear heating occur in the machine components. Magnet insulators that have radiation tolerance to 150 MGy shou
Publikováno v:
Fusion Technology. 39:951-955
High temperature refractory alloys of tungsten, molybdenum and tantalum are under evaluation for use as structural materials in the Advanced Power Extraction Program (APEX) because of their ability to accommodate high wall loading and high temperatur
Autor:
Brad J. Merrill, Nasr M. Ghoniem, E.E. Reis, H.Y. Khater, B.E. Nelson, Mahmoud Z. Youssef, Shahram Sharafat, Steven J. Zinkle, K. McCarthy, S. Willms, P.J. Fogarty, C.B. Baxi, M.A. Ulrickson, D.K. Sze, C.P.C. Wong, R. Schleicher, Richard E. Nygren
Publikováno v:
Fusion Engineering and Design. :709-717
Under the APEX program the He-cooled system design task is to evaluate and recommend high power density refractory alloy first wall and blanket designs and to recommend and initiate tests to address critical issues. We completed the preliminary desig