HYLIFE-II: A Molten-Salt Inertial Fusion Energy Power Plant Design — Final Report

Moir, R.W.; Bieri, R.L.; Chen, X. M.; Dolan, Thomas J.; Hoffman, Matthew; House, P.A.; Leber, R. L.; Lee, J. D.; Lee, Y. T.; Liu, J. C.; Longhurst, G.R.; Meier, W.R.; Peterson, Per F.; Petzoldt, R.W.; Schrock, V.E.; Tobin, Michael T.; Williams, Wade H.

doi:10.13182/fst94-a30234

Cited by 233 publications

(8 citation statements)

References 31 publications

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“…This drastically reduces the lifetime of the reactor. The limit for helium production is suggested as 500 appm [12]. Table VI shows that the helium production limit was reached for the selected heavy metal contents.…”

Section: Discussionmentioning

confidence: 98%

Radiation Damage Investigation on Certain Alternative Fluids in a Hybrid System by Using MCNPX Monte Carlo Radiation Transport Code

Günay

2015

Acta Phys. Pol. A

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In this study, the effect of the radiation damage of spent fuel-grade plutonium content was investigated in the structural material of a designed fusion-fission hybrid reactor system. In this study, the molten salt-heavy metal mixtures 99-95% Li20Sn80-1-5% SFG-Pu, 99-95% Li20Sn80-1-5% SFG-PuF4, and 99-95% Li20Sn80-1-5% SFG-PuO2 were used as fluids. The fluids were used in the liquid first-wall, blanket and shield zones of the designed hybrid reactor system. Four centimeter thick 9Cr2WVTa ferritic steel was used as the structural material. Proton, deuterium, tritium, He-3 and He-4 gas production rates are the parameters of radiation damage. In this study, damage to the total structural material and each 1.0 cm thickness thereof was measured as a function of radiation energy, using the selected fluid rates, for 30 full power years (FPYs). Three-dimensional analyses were performed using the most recent MCNPX-2.7.0 Monte Carlo radiation transport code and the ENDF/B-VII.0 nuclear data library.

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Section: Discussionmentioning

confidence: 98%

Radiation Damage Investigation on Certain Alternative Fluids in a Hybrid System by Using MCNPX Monte Carlo Radiation Transport Code

Günay

2015

Acta Phys. Pol. A

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“…The heat that is applied at the target surface conducts into the portions of the target containing DT. (Calculations show that current designs of indirect drive targets [2] injected into liquid wall chambers [3,4] do not show any significant heating of the DT ice. This is a result of protection provided by the low thermal conductivity materials used in the hohlraum construction.)…”

Section: Target Heating During Injectionmentioning

confidence: 96%

“…The design yield of this target is 436 MJ with a gain of 133 using a 3.3 MJ driver. While IFE power plant design studies [3,4] have suggested potentially plausible scenarios for both direct drive and indirect drive target injection, the purpose of the development program described in this paper is to provide the detailed scientific basis that will be necessary for fueling of future IFE power plants. This paper presents the requirements and key issues that have been identified for IFE target injection, summarizes the modeling and analyses that have been done, and presents the development program that is planned to assure that target injection can be successfully accomplished.…”

Section: Introductionmentioning

confidence: 99%

Developing target injection and tracking for inertial fusion energy power plants

et al. 2001

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Fueling of a commercial Inertial Fusion Energy (IFE) power plant consists of supplying about 500,000 fusion targets each day. The most challenging type of target in this regard is for laserdriven, direct drive IFE. Spherical capsules with cryogenic DT fuel must be injected into the center of a reaction chamber operating at temperatures as high as 1500°C and possibly containing as much as 0.5 Torr of xenon fill gas. The DT layer must remain highly symmetric, have a smooth inner ice surface finish, and reach the chamber center (CC) at a temperature of about 18.5 K. This target must be positioned at the center of the chamber with a placement accuracy of ±5 mm. The accuracy of alignment of the laser driver beams and the target in its final position must be within ±20 µm. All this must be repeated six times per second. The method proposed to meet these requirements is injecting the targets into the reaction chamber at high speed (~400 m/s), tracking them, and hitting them on the fly with steerable driver beams. The challenging scientific and technological issues associated with this task are being addressed through a combination of analyses, modeling, materials property measurements, and demonstration tests with representative injection equipment. Measurements of relevant DT properties are planned at Los Alamos National Laboratory. An experimental target injection and tracking system is now being designed to support the development of survivable targets and demonstrate successful injection scenarios. Analyses of target heating are underway. Calculations have shown that the direct drive target must have a highly reflective outer surface to prevent excess heating by thermal radiation. In addition, heating by hot chamber fill gas during injection far outweighs the thermal radiation. It is concluded that the dry-wall, gasfilled reaction chambers must have gas pressures and wall temperatures less than previously assumed in order to prevent excessive heating in the current direct drive target designs. An integrated power plant systems study to address this issue has been initiated.

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“…Heavy-ion inertial fusion has attractive prospects for generating electrical power at reasonable cost, with high availability, safety, and low activation [1,3,4]. Advantages with HIF accrue from the separability of the driver and the target factory from the chamber and the protection of chamber walls from radiation by thick liquid walls.…”

Section: Introductionmentioning

confidence: 99%

“…Furthermore, within the driver, components such as quadrupole magnets and induction cells are replicated thousands of times, leading to low development costs and easier maintenance. The thick liquid walls are composed of flibe, a low-activation molten salt containing fluorine, lithium, and beryllium [3,4]. They are typically formed from static or oscillating jets [5] of flibe, which shield the solid walls of the vacuum chamber from neutrons and gamma rays and also generate tritium from neutron interactions with the lithium in a continuously replaced blanket.…”

Section: Introductionmentioning

confidence: 99%

Induction core alloys for heavy-ion inertial fusion-energy accelerators

Molvik

Faltens

2002

Phys. Rev. ST Accel. Beams

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Induction core alloys are evaluated that are appropriate for heavy-ion induction accelerators to drive heavy-ion inertial fusion (HIF) power plants. Parameters evaluated include the usable flux swing and the energy loss over a range of magnetization rates of ϳ10 5 10 7 T͞s, corresponding to pulse durations of ϳ20 to 0.2 ms, respectively. The usable flux swing, for minimum core losses, extends from near the reversed remanent field to about 80% of the saturation field. The usable flux swing is enhanced, with little increase in losses, by annealing the core after winding. Maintaining low energy loss at high magnetization rates requires insulation to block interlaminar eddy currents. To obtain annealed cores with a high ratio of remanent to saturation magnetic field, the insulation must withstand annealing temperatures and apply minimum mechanical stress to the core during cooldown. We find that commercially available insulating coatings for amorphous metals either break down near 10 6 T͞s (a factor of 10 below the requirement), or do not achieve the maximum remanent field and hence the usable flux swing after annealing. More satisfactory coatings are available for silicon steel and nanocrystalline alloys, which could have applications in HIF. Amorphous alloys are capable of meeting most HIF needs, especially with improved coatings.

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HYLIFE-II: A Molten-Salt Inertial Fusion Energy Power Plant Design — Final Report

Cited by 233 publications

References 31 publications

Radiation Damage Investigation on Certain Alternative Fluids in a Hybrid System by Using MCNPX Monte Carlo Radiation Transport Code

Radiation Damage Investigation on Certain Alternative Fluids in a Hybrid System by Using MCNPX Monte Carlo Radiation Transport Code

Developing target injection and tracking for inertial fusion energy power plants

Induction core alloys for heavy-ion inertial fusion-energy accelerators

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