HYLIFE-II: A Molten-Salt Inertial Fusion Energy Power Plant Design — Final Report
TL;DR: 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.« less
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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.
115 citations
Cites background from "HYLIFE-II: A Molten-Salt Inertial F..."
...breeder jets to protect the chamber metallic wall such as in the HYLIFE-II inertial fusion (IFE) chamber [8] and magnetic fusion (MFE) liquid wall concepts [9] have high breeding potential due to elimination of structural material from the front breeding zone....
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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.
Abstract: Recent progress in laser driven implosion is reviewed. Improvements in the uniformity of irradiation by laser beams on fuel pellets have achieved quantitative progress in implosion performance. The recent results of the direct drive–central ignition experiments give us confidence in achieving fusion ignition, burning and energy gain using a multi-beam megajoule laser with full implementation of beam smoothing techniques. Fast ignition research is also reviewed, which could give us a higher energy gain with lower laser energy. The science and technology of laser fusion power plants are beginning to attract wider attention, as forming the road map to achieve commercial power plants for cleaner, safer and abundant fusion energy.Corrections were made to this article on 28 April 2004
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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.
101 citations
Cites background from "HYLIFE-II: A Molten-Salt Inertial F..."
..., but also the study of new type fissile producers including DT-fusion facilities should be pursued applying (i) inertial confinement fusion [33], and (ii) magnetic fusion....
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18 Dec 1998
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.
Abstract: This paper reviews work on flashlamp-pumped solid state lasers and discusses diode-pumped solid state lasers, the Mercury laser in particular. It also discusses ICF lasers beyond Mercury.
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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).
Abstract: A comprehensive conceptual design for a diode pumped solid state laser (DPSSL) as a driver for an inertial fusion energy (IFE) power plant is presented. This design is based on recent technical advances that offer potential solutions to difficulties previously associated with the use of a laser for IFE applications. The design was selected by using a systems analysis code that optimizes a DPSSL configuration by minimizing the calculated cost of electricity (COE). The code contains the significant physics relevant to the DPSSL driver, but treats the target chamber and balance of plant costs generically using scaling relations published for the Sombrero KrF laser concept. The authors describe the physics incorporated in the code, predict DPSSL performance and its variations with changes in the major parameters, discuss IFE economics and technical risk, and identify the high leverage development efforts that can make DPSSL driven IFE plants more economically competitive. It is believed that this study is a significant advance over previous conceptual studies of DPSSLs for IFE because it incorporates a new cost effective gain medium, applies a potential solution to the `final optics` problem, and considers the laser physics in substantially greater detail. The result is the introduction of an option for an IFE driver that has relatively low development costs and that builds upon the mature laser technology base already developed for Nova and being developed for the proposed National Ignition Facility. The baseline design of the paper has a product of laser efficiency and target gain of ηG~6.6 and a COE of 8.6 cents/kW.h for a 1 GW(e) plant with a target gain of 76 at 3.7 MJ. Higher ηG(11) and lower COEs (6.6 cents/kW.h) can be achieved with target gains twice as high
92 citations
References
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23 Dec 1985
TL;DR: The High-Yield Lithium-Injection Fusion Energy (HYLIFE) concept to convent inertial confinement fusion energy into electric power has undergone intensive research and refinement at LLNL since 1978 as discussed by the authors, focusing on the HYLIFE reaction chamber (which includes neutronics, liquid-metal jet-array hydrocynamics, and structural design), supporting systems, primary steam system and balance of plant, safety and environmental protection, and costs.
Abstract: The High-Yield Lithium-Injection Fusion Energy (HYLIFE) concept to convent inertial confinement fusion energy into electric power has undergone intensive research and refinement at LLNL since 1978. This paper reports on the final HYLIFE design, focusing on five major areas: the HYLIFE reaction chamber (which includes neutronics, liquid-metal jet-array hydrocynamics, and structural design), supporting systems, primary steam system and balance of plant, safety and environmental protection, and costs. An annotated bibliography of reports applicable to HYLIFE is also provided. We conclude that HYLIFE is a particularly viable concept for the safe, clean production of electrical energy. The liquid-metal jet array, HYLIFE's key design feature, protects the surrounding structural components from x-rays, fusion fuel-pellet debris, neutron damage and activation, and high temperatures and stresses, allowing the structure to last for the plant's entire 30-year lifetime without being replaced. 127 refs., 18 figs.
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TL;DR: The initial scoping analysis indicates that by using Type 304 stainless steel (SS), most of the vacuum vessel's structural mass in the HYLIFE-II inertial fusion energy power plant conceptual design cou....
Abstract: Initial scoping analysis indicates that by using Type 304 stainless steel (SS), most of the vacuum vessel’s structural mass in the HYLIFE-II inertial fusion energy power plant conceptual design cou...
50 citations
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TL;DR: The HYLIFE-II inertial fusion power plant design study uses a liquid fall, in the form of jets to protect the first structural wall from neutron damage, x-rays, and blast to provide a 30-y lifetime.
Abstract: The HYLIFE-II inertial fusion power plant design study uses a liquid fall, in the form of jets to protect the first structural wall from neutron damage, x-rays, and blast to provide a 30-y lifetime. HYLIFE-I used liquid lithium. HYLIFE-II avoids the fire hazard of lithium by using a molten salt composed of fluorine, lithium, and beryllium (Li{sub 2}BeF{sub 4}) called Flibe. Access for heavy-ion beams is provided. Calculations for assumed heavy-ion beam performance show a nominal gain of 70 at 5 MJ producing 350 MJ, about 5.2 times less yield than the 1.8 GJ from a driver energy of 4.5 MJ with gain of 400 for HYLIFE-I. The nominal 1 GWe of power can be maintained by increasing the repetition rate by a factor of about 5.2, from 1.5 to 8 Hz. A higher repetition rate requires faster re-establishment of the jets after a shot, which can be accomplished in part by decreasing the jet fall height and increasing the jet flow velocity. Multiple chambers may be required. In addition, although not considered for HYLIFE-I, there is undoubtedly liquid splash that must be forcibly cleared because gravity is too slow, especially at high repetition rates. Splash removal can be accomplishedmore » by either pulsed or oscillating jet flows. The cost of electricity is estimated to be 0.09$/kW{center dot}h in constant 1988 dollars, about twice that of future coal and light water reactor nuclear power. The driver beam cost is about one-half the total cost. 12 refs., 9 figs., 5 tabs.« less
39 citations
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TL;DR: In this article, an inertial fusion power plant design study uses a liquid fall, in the form of jets, to protect the first structural wall from neutron damage, x rays, and blast to provide a 30-y lifetime.
Abstract: The HYLIFE-II inertial fusion power plant design study uses a liquid fall, in the form of jets, to protect the first structural wall from neutron damage, x rays, and blast to provide a 30-y lifetime. HYLIFE-I used liquid lithium. HYLIFE-II avoids the fire hazard of lithium by using a molten salt composed of fluorine, lithium, and beryllium (Li2BeF4) called Flibe. Access for heavy-ion beams is provided. Calculations for assumed heavy-ion beam performance show a nominal gain of 70 at 5 MJ producing 350 MJ, about 5.2 times less yield than the 1.8 GJ from a driver energy of 4.5 MJ with gain of 400 for HYLIFE-I. The nominal 1 GWe of power can be maintained by increasing the repetition rate by a factor of about 5.2, from 1.5 to 8 Hz. A higher repetition rate requires faster re-establishment of the jets after a shot, which can be accomplished in part by decreasing the jet fall height and increasing the jet flow velocity. In addition, although not adequately considered for FIYLIFE-I, there is liquid splas...
35 citations
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TL;DR: In this article, the projected cost of electricity (COE) for fusion is compared with that from current and advanced nuclear fission and coal-fired plants, and the results show COEs of about 59--74 mills/kWh for the fusion designs considered.
Abstract: The projected cost of electricity (COE) for fusion is compared with that from current and advanced nuclear fission and coal-fired plants. Fusion cost models were adjusted for consistency with advanced fission plants and the calculational methodology and cost factors follow guidelines recommended for cost comparisons of advanced fission reactors. The results show COEs of about 59--74 mills/kWh for the fusion designs considered. In comparison, COEs for future fission reactors are estimated to be in the 43--54 mills/kWh range with coal-fired plant COEs of about 53--69 mills/kWh ($2--3/GJ coal). The principal cost driver for the fusion plants relative to fission plants is the fusion island cost. Although the estimated COEs for fusion are greater than those for fission or coal, the costs are not so high as to preclude fusion's competitiveness as a safe and environmentally sound alternative.
31 citations