Journal ArticleDOI
HYLIFE-II: A Molten-Salt Inertial Fusion Energy Power Plant Design — Final Report
Ralph W. Moir,R. L. Bieri,Xiang M. Chen,T. J. Dolan,M. A. Hoffman,P.A. House,R. L. Leber,J. D. Lee,Y. T. Lee,J. C. Liu,G. R. Longhurst,Wayne R. Meier,P. F. Peterson,Ronald W. Petzoldt,V. E. Schrock,M. Tobin,W. H. Williams +16 more
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TLDR
In this article, the liquid-wall HYLIFE-II conceptual design has been presented, which has been shown to reduce the electricity cost by using a neutronically thick array of flowing molten-salt jets, which will not burn, has a low tritium solubility and inventory, and protects the chamber walls.Abstract:
Enhanced safety and performance improvements have been made to the liquid-wall HYLIFE reactor, yielding the current HYLIFE-II conceptual design. Liquid lithium has been replaced with a neutronically thick array of flowing molten-salt jets (Li[sub 2]BeF[sub 4] or Flibe), which will not burn, has a low tritium solubility and inventory, and protects the chamber walls, giving a robust design with a 30-yr lifetime. The tritium inventory is 0.5 g in the molten salt and 140 g in the metal of the tube walls, where it is less easily released. The 5-MJ driver is a recirculating induction accelerator estimated to cost $570 million (direct costs). Heavy-ion targets yield 350 MJ, six times per second, to produce 940 MW of electrical power for a cost of 6.5 cents/kW[center dot]h. Both larger and smaller yields are possible with correspondingly lower and higher pulse rates. When scaled up to 1934 MW (electric), the plant design has a calculated cost of electricity of 4.5 cents/kW[center dot]h. The design did not take into account potential improved plant availability and lower operations and maintenance costs compared with conventional power plant experience, resulting from the liquid wall protection. Such improvements would directly lower the electricity cost figures. For example,more » if the availability can be raised from the conservatively assumed 75% to 85% and the annual cost of component replacement, operations, and maintenance can be reduced from 6% to 3% of direct cost, the cost of electricity would drop to 5.0 and 3.9 cents/kW[center dot]h for 1- and 2-GW (electric) cases. 50 refs., 15 figs., 3 tabs.« lessread more
Citations
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Journal ArticleDOI
Physics and technology conditions for attaining tritium self-sufficiency for the DT fuel cycle
TL;DR: In this paper, the potential of achieving tritium self-sufficiency depends on many system physics and technology parameters, and Interactive Physics and Technology R&D programs should be implemented to determine the potential to realize those physics and technologies options and parameters that have large effects on attaining a realistic window for tritiam self-sufficiency.
Journal ArticleDOI
Laser driven inertial fusion energy: present and prospective
TL;DR: In this paper, a review of recent progress in laser driven implosion is reviewed, showing that improvements in the uniformity of irradiation by laser beams on fuel pellets have achieved quantitative progress in implosion performance.
Journal ArticleDOI
A Road Map for the Realization of Global-scale Thorium Breeding Fuel Cycle by Single Molten-Fluoride Flow
Kazuo Furukawa,Kazuto Arakawa,L. Berrin Erbay,Yasuhiko Ito,Yoshio Kato,H. Kiyavitskaya,Alfred Lecocq,Koshi Mitachi,Ralph Moir,Hiroo Numata,J. Paul Pleasant,Yuzuru Sato,Yoichiro Shimazu,Vadim A. Simonenco,Din Dayal Sood,Carlos Urban,Ritsuo Yoshioka +16 more
TL;DR: The Thorium Molten Salt Nuclear Energy Synergetic System [THORIMS-NES] as mentioned in this paper is a symbiotic system, based on the thorium-uranium-233 cycle.
Diode-pumped solid-state laser drivers for inertial fusion energy
TL;DR: In this article, the authors review work on flashlamp-pumped solid state lasers and discuss diode-pump solid state laser, the Mercury laser in particular, and discuss ICF lasers beyond Mercury.
Journal ArticleDOI
A diode pumped solid state laser driver for inertial fusion energy
TL;DR: In this article, a diode pumped solid state laser (DPSSL) was used as a driver for an inertial fusion energy (IFE) power plant to minimize the calculated cost of electricity (COE).
References
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Journal ArticleDOI
An approximate method for analyzing transient condensation on spray in HYLIFE-II
R.Y. Bai,Virgil E. Schrock +1 more
TL;DR: The HYLIFE-II conceptual design called for analysis of highly transient condensation on droplets to achieve a rapidly decaying pressure field as mentioned in this paper, where drops exposed to the required transient vapor pressure field are first heated by condensation but later begin to reevaporate after the vapor temperature falls below the drop surface temperature.
Journal ArticleDOI
The pressure relaxation of liquid jets after isochoric heating
Xiang M. Chen,Virgil E. Schrock +1 more
TL;DR: In this paper, the mechanism of the relaxation of liquid jets after isochoric heating has been studied with both incompressible and compressible models and reveals a strongly peaked tension in the wake of a rarefaction wave.
Journal ArticleDOI
Safety and Environmental Aspects of HYLIFE-II
T. J. Dolan,G. R. Longhurst +1 more
TL;DR: In this paper, the authors quantified the required tritium removal efficiencies for a severe accident involving simultaneous failure of the blast chamber and containment building in the HYLIFE-II inertial confinement fusion reactor.
Journal ArticleDOI
Performance and Cost of the HYLIFE-II Balance of Plant
M.A. Hoffman,Y.T. Lee +1 more
TL;DR: The HYLIFE-II concept uses the molten salt, Flibe as the primary coolant for the liquid jet flows in the reactor and uses sodium fluoroborate (NaBF4) in the secondary loop as discussed by the authors.
Journal ArticleDOI
Transport processes in an inertial confinement fusion reactor
TL;DR: In this paper, a quasi-one-dimensional method for calculating a transient, compressible, viscous flow through a complex array of tubes or jets was extended to include heat and mass exchange between the fluid and the jets.
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