Design of the national compact stellarator experiment (NCSX)

Nelson, B.; Berry, L. A.; Brooks, A.; Cole, M. J.; Chrzanowski, J.; Fan, Haiyang; Fogarty, P.J.; Goranson, P.; Heitzenroeder, P.; Hirshman, S. P.; Jones, G. H.; Lyon, J. F.; Neilson, G.H.; Reiersen, W.; Strickler, D. J.; Williamson, D.

doi:10.1016/s0920-3796(03)00183-2

Cited by 50 publications

(39 citation statements)

References 2 publications

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“…Traditionally, modular stellarator experiments 5,8,9 and conceptual power plant designs 1,6 have a magnet system such that each coil is in its own casing, in shape similar to the coil shape, with structural connections between adjacent coil structures to form a trusslike field period structural assembly. Fabrication and assembly techniques on current stellarator experiments have resulted in the coil structure being one of the more expensive power core components.…”

Section: Introductionmentioning

confidence: 99%

ARIES-CS Magnet Conductor and Structure Evaluation

Wang

Raffray

Bromberg

et al. 2008

Fusion Science and Technology

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Section: Introductionmentioning

confidence: 99%

ARIES-CS Magnet Conductor and Structure Evaluation

Wang

Raffray

Bromberg

et al. 2008

Fusion Science and Technology

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“…Newer experiments are the National Spherical Torus Experiment (NSTX) (Neumeyer, 1999) and the National Compact Stellarator Experiment (NCSX) (Nelson, 2003). A time line of some of the major experiments at PPPL (Tanner, 1982) is:…”

Section: Princeton Plasma Physics Laboratorymentioning

confidence: 99%

Occupational Safety Review of High Technology Facilities

Cadwallader¹

2005

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This report contains reviews of operating experiences, selected accident events, and industrial safety performance indicators that document the performance of the major US DOE magnetic fusion experiments and particle accelerators. These data are useful to form a basis for the occupational safety level at matured research facilities with known sets of safety rules and regulations. Some of the issues discussed are radiation safety, electromagnetic energy exposure events, and some of the more widespread issues of working at height, equipment fires, confined space work, electrical work, and other industrial hazards. Nuclear power plant industrial safety data are also included for comparison.ii SUMMARY An issue of interest with the International Thermonuclear Experimental Reactor (ITER) design is the safety of the personnel who will operate and maintain the facility. Since the ITER machine is much larger than existing experiments and will handle higher power levels and input energies than present tokamaks, there is a concern that the personnel will be at higher risk than the presently accepted levels of risk seen in the existing fusion experiments. The existing US tokamaks have not had any personnel fatalities, and severe occupational accidents have also been rare. Similar operating experiences with the largest US particle accelerators have had fatalities during construction, but have experienced any fatalities in operation. The accelerators have had a few severe occupational accidents. The accelerators and fusion experiments have had occupational injury rates that were somewhat higher than other DOE research and development facilities. In recent years, the fission power plants have had lower occupational accident/injury rates than either fusion or the accelerators, but the power plant accident severity may be greater, and the power plants have had some occupational fatalities while fusion and accelerator operations have not. These data, along with safety performance statistics, have been documented in this report. The case history descriptions presented here are useful to understand the types of occupational events that have occurred and the energy sources involved in the events. These data will support occupational safety analysis of ITER operations, especially a room-by-room analysis of energies and hazards that ITER workers will experience during plant operation and maintenance. The safety performance statistics presented here highlight areas for improvement in occupational safety at fusion and accelerator facilities; ITER can use these data to form more robust occupational safety programs. The statistics also support setting occupational safety goals for ITER operation. Due to its size and power levels, ITER is envisioned to be greater than existing fusion experiments but less than a nuclear fission power plant, and safety goals can be set accordingly.iii CONTENTS ABSTRACT

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“…In the divertor design, we aim for an optimal plate location and surface topology that will result in the lowest possible fl, thus allowing the divertor to handle high heat with the least amount of high-Z plate material. On the other hand, noting that Pdiv (= 1-frc)(Ibfrd)Pa (2) where P,, is the net alpha heating power, fre is the core radiation fraction, and frd is the fraction of power radiated from the divertor/SOL region, the divertor power can be reduced by operating with higher core and SOL radiation. The former may be achieved by setting up a radiating mantle just inside the LCMS while the latter may require the divertor to operate in the high-recycling or semi-detached regime.…”

Section: Divertor Design Criteria and Toolsmentioning

confidence: 99%

“…TARGET PLATE INVESTIGATION RESULTS For our initial divertor study, we employed an example CS magnetic configuration based on NCSX [2], that has 3 field periods, 18 modular coils, D = 4% and an aspect ratio of 4.5. The scaled-up reactor has <R> = 8.25 m, <a> = 1.85 m, B = 5.3 T on axis, and a net electric power output of 1 GW.…”

Section: IIImentioning

confidence: 99%

“…In this paper, we report initial results of an exploratory study of divertor location, size and surface topology, and the corresponding heat load distribution for an example NCSXbased [2] CS configuration with 3 field periods, 18 modular coils, and a major radius of 8.25 m. We also present results of ongoing work aimed at assessing alpha-particle heat fluxes that may impact the divertor configuration. In Section II we describe the assumptions and methodology in the divertor study and the computational tools used for the analysis.…”

Section: Introductionmentioning

confidence: 99%

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Exploratory Divertor Heat Load Studies for Compact Stellarator Reactors

Mau

McGuinness

Grossman

et al. 2005

21st IEEE/NPS Symposium on Fusion Engineering SOFE 05

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Divertor heat load evaluation studies are being carried out for an example compact stellarator reactor configuration modeled after the National Compact Stellarator Experiment (NCSX). Using the field line tracing technique, an initial divertor plate geometry has been obtained, with one plate per field period, which covers 15% of the plasma surface area. A plate heat load peaking factor of 14 is acceptable with reasonable core and SOL radiation fractions in order to satisfy the engineering constraint of 10 MW/M2 peak heat load. Assessment of heat flux due to ejected energetic alpha particles is equally important for their contribution to the heat load. A particle gyro-orbit code follows these particles in the scrape-off layer (SOL) until they hit the divertor plates and the first wall, while the distribution of lost particles on the plasma surface can be calculated with a Monte Carlo guiding center code with collisions.

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Design of the national compact stellarator experiment (NCSX)

Cited by 50 publications

References 2 publications

ARIES-CS Magnet Conductor and Structure Evaluation

ARIES-CS Magnet Conductor and Structure Evaluation

Occupational Safety Review of High Technology Facilities

Exploratory Divertor Heat Load Studies for Compact Stellarator Reactors

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