ARIES-CS Maintenance System Definition and Analysis

Waganer, Lester M.; Peipert, R. J.; Wang, Xueren R.; Malang, S.; Team, Aries

doi:10.13182/fst08-a1904

Cited by 18 publications

(3 citation statements)

References 11 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…A discount rate of 10% is employed, assuming that high risk is expected due to the initial introduction of fusion deployment, and 15% of the hybrid system TCI for salvage rate is applied 94 . The capacity of the biomass plant inherently account for an annual 7446 hours (approximate 85% of a year), which is for equipment refurbishment and replacement for the hybrid system 95,96 . The double balance method and 30% of income tax is assumed.…”

Section: Methodsmentioning

confidence: 99%

Techno‐economic analysis of hydrogen production from the nuclear fusion‐biomass hybrid system

Nam

Konishi

2020

Int J Energy Res

View full text Add to dashboard Cite

Summary The hydrogen production over the combination of nuclear fusion and biomass conversion technologies achieves the carbon‐negative effect by employing carbon capture and storage technology. Techno‐economic analysis on the fusion‐biomass hybrid system is performed to understand the hydrogen cost and the cost competitiveness as compared to other existing technologies. Cellulose, hemicellulose, and lignin for biomass are chosen for the techno‐economic analysis in addition to the municipal solid waste as another feedstock. Stoichiometric calculation for biomass conversion to hydrogen is employed. Nuclear fusion thermal heat capacity and its heat cost are selected based on literature survey. Gasification plant for hydrogen production is assumed to employ the bubbling fluidized bed gasifier, fed by 20.6 MJ/kg of biomass. The result shows that total syngas capacity is 203 PJ and 137 PJ of hydrogen is produced through a ceramic membrane for H2 separation. The levelized cost of hydrogen is $2.45/kg and the estimated 90% confidence interval of the LCOH ranges from $1.87 to $3.24/kg. The LCOH locates at a competitive position among the existing technologies. The LCOH can further decreased with the development of carbon pricing by the time of fusion commercialization in 2050.

show abstract

Section: Methodsmentioning

confidence: 99%

Techno‐economic analysis of hydrogen production from the nuclear fusion‐biomass hybrid system

Nam

Konishi

2020

Int J Energy Res

View full text Add to dashboard Cite

show abstract

“…Maintaining and replacing stellarator components can be considerably more challenging compared to tokamaks if the access to internal elements is limited by the lateral space between modular coils [112]. This space determines the maximum dimensions of blanket and divertor modules.…”

Section: Fabrication Integration and Maintenancementioning

confidence: 99%

Stellarator Research Opportunities: A Report of the National Stellarator Coordinating Committee

Gates

Anderson

et al. 2018

J Fusion Energ

View full text Add to dashboard Cite

This document is the product of a stellarator community workshop, organized by the National Stellarator Coordinating Committee and referred to as Stellcon, that was held in Cambridge, Massachusetts in February 2016, hosted by MIT. The workshop was widely advertised, and was attended by 40 scientists from 12 different institutions including national labs, universities and private industry, as well as a representative from the Department of Energy. The final section of this document describes areas of community wide consensus that were developed as a result of the discussions held at that workshop. Areas where further study would be helpful to generate a consensus path forward for the US stellarator program are also discussed.The program outlined in this document is directly responsive to many of the strategic priorities of FES as articulated in "Fusion Energy Sciences: A Ten-Year Perspective (2015-2025)" [1]. The natural disruption immunity of the stellarator directly addresses "Elimination of transient events that can be deleterious to toroidal fusion plasma confinement devices" an area of critical importance for the U.S. fusion energy sciences enterprise over the next decade.

show abstract

“…Design studies advancing high availability have been undertaken for a number of years within the fusion community incorporating a range of configuration arrangements with varying maintenance concepts [6][7][8][9][10][11][12][13][14][15][16][17][18]. Reasonable availability was evaluated in an ARIES-CS stellarator study [12][13] which incorporated an ITER style port maintenance scheme, assuming a tenth of a kind plant and optimistic maintenance assumptions.…”

Section: Configuration Concepts and Design Philosophymentioning

confidence: 99%

Comparison of Options for a Pilot Plant Fusion Nuclear Mission

Brown

Costley

Goldston

et al. 2013

Fusion Science and Technology

View full text Add to dashboard Cite

ARIES-CS Maintenance System Definition and Analysis

Abstract: The goal of the ARIES compact stellarator is to define and assess a stellarator-based fusion power plant to

Cited by 18 publications

References 11 publications

Techno‐economic analysis of hydrogen production from the nuclear fusion‐biomass hybrid system

Techno‐economic analysis of hydrogen production from the nuclear fusion‐biomass hybrid system

Stellarator Research Opportunities: A Report of the National Stellarator Coordinating Committee

Comparison of Options for a Pilot Plant Fusion Nuclear Mission

Contact Info

Product

Resources

About