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An outboard shield design for TIBER-II with potential for tritium self-sufficiency: Appendix A-1

Description: The outboard breeding shield design for TIBER-II is described. The design allows for tritium self-sufficiency without compromising magnet protection, design simplicity, and the testing mission of the device. The shield consists of a beryllium pebble front zone backed by a steel pebble zone. The shield is cooled by an aqueous solution containing 16 g LiNO/sub 3/ per 100 cm/sup 3/. A double first wall is used to insure uniform cooling and minimize pressure. The design pressure for the outboard shield is 0.19 MPa and the coolant temperature is less than 75/sup 0/C. 6 refs., 5 figs., 3 tabs.
Date: January 1, 1987
Creator: Sawan, M.E. & Sviatoslavsky, I.N.
Partner: UNT Libraries Government Documents Department

Impact of transmutations in fusion environment on Flibe chemistry.

Description: Transmutation rates of Li, Be and F are calculated for a typical flibe blanket. The results concluded that the transmutation rate of F is more than double that of Be. Because of the high destruction rate of fluorine, there will be no free fluorine in the molten salt. Therefore, experimental program to address the chemistry control of flibe does not have to worry about the issues associated with free fluorine. Also, this calculation defines the chemical of flibe after irradiation. This chemical state needs to be simulated closely for the flibe chemistry control experiment.
Date: November 15, 2000
Creator: Sze, D. K.; Sawan, M. E. & Cheng, E. T.
Partner: UNT Libraries Government Documents Department

Shielding analysis for a heavy ion beam chamber with plasma channels for ion transport

Description: Neutronics analysis has been performed to assess the shielding requirements for the insulators and final focusing magnets in a modified HYLIFE-II target chamber that utilizes pre-formed plasma channels for heavy ion beam transport. Using 65 cm thick Flibe jet assemblies provides adequate shielding for the electrical insulator units. Additional shielding is needed in front of the final focusing superconducting quadrupole magnets. A shield with a thickness varying between 45 and 90 cm needs to be provided in front of the quadrupole unit. The final laser mirrors located along the channel axis are in the direct line-of-sight of source neutrons. Neutronics calculations were performed to determine the constraints on the placement of these mirrors to be lifetime components.
Date: June 28, 2000
Creator: Sawan, M.E.; Peterson, R.R. & Yu, S.
Partner: UNT Libraries Government Documents Department

Nuclear Analysis for Near Term Fusion Devices

Description: A Next Step Options (NSO) study was initiated to consider the logical steps that might be undertaken to restructure the U.S. Fusion Sciences Program. Most of the effort was concentrated on designing the Fusion Ignition Research Experiment (FIRE), which is in the preconceptual design phase. It utilizes 16 cryogenically cooled wedged copper TF coils with beryllium copper in the inner legs and OFHC copper in the outer legs. We provided significant contributions in the areas of neutronics, shielding and activation analyses. The design went through different changes. Early in the year 2002 the baseline design changed from a major radius of 2 m to a major radius of 2.14 m and an aspect ratio of 3.6. In addition the fusion power during the DT pulses changed from 200 MW to 150 MW. We spent significant part of the effort calculating the nuclear performance parameters for the final baseline design. While pulses producing a total of 5 TJ of DT fusion energy and 0.5 TJ of DD fusion energy were considered in the previous designs, a detailed experimental plan was developed that results in higher total fusion energy. We assessed the impact on the peak magnet insulator dose. Multi-dimensional calculations were performed also to determine the impact of plasma shape and profile on he peak radiation effects in the TF coils. We performed multi-dimensional calculations for one of the most critical diagnostics ports to assess streaming and determine the nuclear environment at the sensitive components. The radwaste level and volume was quantified for the different components of FIRE.
Date: April 2, 2007
Creator: Sawan, M.E.; Kulcinski, G.L. & Henderson, D.L.
Partner: UNT Libraries Government Documents Department

Ra: A high efficiency, D-/sup 3/He, tandem mirror fusion reactor: Appendix C

Description: The Ra tandem mirror fusion reactor concept features inherent safety, high net plant efficiency, low cost of electricity, low radioactive waste generation, low activation, highly efficient direct conversion, thin radiation shields, and axisymmetric magnets. The safety and environmental features are achieved through the use of D/He-3 fuel, while the high efficiency derives from a new operating mode. ICRF stabilization allows an axisymmetric magnet set. 11 refs., 5 figs., 3 tabs.
Date: January 1, 1987
Creator: Santarius, J.F.; Attaya, H.; Corradini, M.L.; El-Guebaly, L.A.; Emmert, G.A.; Kulcinski, G.L. et al.
Partner: UNT Libraries Government Documents Department

A light ion beam driver for the Laboratory Microfusion Facility

Description: The Laboratory Microfusion Facility (LMF) is being planned to develop high-grain, high-yield (200 MJ-1000 MJ) ICF targets for applications to nuclear weapons effects simulation, thermonuclear weapons physics, and energy production. It is expected that a 1000-MJ yield will require {approximately}10--20 MJ input energy to the target. The light-ion beam driver concept for the LMF consists of 36 accelerator modules that drive independent Li{sup +} ion diodes. Each ion beam is extracted from an annular ion diode and propagated to a solenoidal lens located near the wall of the target chamber. This magnetic lens focuses the beam on to the pellet located at the center of the target chamber. The temporal shape of the power pulse delivered to the target is controlled by the synchronized firing of the accelerator modules. This paper presents a status of the light-ion beam LMF driver concept.
Date: January 1, 1990
Creator: Ramirez, J.J.; Prestwich, K.R.; Stinnett, R.W.; Johnson, D.L.; Olson, C.L.; Allshouse, G.O. et al.
Partner: UNT Libraries Government Documents Department