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

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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.« less

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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.

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

Targets for Heavy Ion Fusion

TL;DR: In the Heavy Ion Fusion Systems Assessment Project (HIIPSA) as mentioned in this paper, improved target concepts to be used in the ''heavy ion fusion systems assessment project'' have been studied.
Journal ArticleDOI

HYLIFE-II Reactor Chamber Mechanical Design

TL;DR: In this paper, a combination of oscillating and steady, molten salt streams are used for the HYLIFE-II inertial confinement fusion power plant, which is the first one to operate in the US.
Journal ArticleDOI

A vacuum disengager for tritium removal from HYLIFE-II Reactor Flibe

TL;DR: In this article, a two-stage vacuum disengager is used to remove tritium from the Flibe (Li sub 2,BeF{sub 4}) molten salt coolant of the HYLIFE-II fusion reactor.
Journal ArticleDOI

Blast venting through blanket material in the HYLIFE ICF reactor

TL;DR: In this article, a numerical study of blast venting through various blanket configurations in the HYLIFE ICF reactor design is presented, where the authors use TSUNAMI, a multi-dimensional, high-resolution, shock capturing code, to predict the momentum exchange and gas dynamics for blast ventilation in complex geometries.
Journal ArticleDOI

Neutronics analysis for HYLIFE-II

Michael T. Tobin
- 01 May 1991 - 
TL;DR: A preliminary neutronics analysis of the HYLIFE-2 reactor concept gives a tritium breeding ratio of 1.17 and a system energy multiplication factor of 2.14 as discussed by the authors.
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