A5038869353- Superconducting Materials and Applications
- Fusion materials and technologies
- Magnetic confinement fusion research
- Nuclear Materials and Properties
- Particle accelerators and beam dynamics
- Spacecraft and Cryogenic Technologies
- Nuclear reactor physics and engineering
- Silicon Carbide Semiconductor Technologies
- Ionosphere and magnetosphere dynamics
- Educational Technology and Assessment
- Nuclear Engineering Thermal-Hydraulics
- Advanced Decision-Making Techniques
- Electromagnetic Launch and Propulsion Technology
- Radiation Effects in Electronics
Southwestern Institute of Physics
2024
University of California, San Diego
2007-2014
An integrated study of compact stellarator power plants, ARIES-CS, has been conducted to explore attractive configurations and define key research development (R&D) areas. The large size mass predicted by earlier plant studies had led cost projections much higher than those the advanced tokamak plant. As such, first major goal ARIES-CS was investigate if plants can be made comparable in variants while maintaining desirable properties. fusion core components would have complex shapes...
Tokamak power plants are studied with advanced and conservative design philosophies to identify the impacts on resulting designs provide guidance critical research needs. Incorporating updated physics understanding using more sophisticated engineering analysis, tokamak configurations have developed a credible basis compared older studies. The configuration assumes self-cooled lead lithium blanket concept SiC composite structural material 58% thermal conversion efficiency. This plasma has...
AbstractThe ARIES-CS team has concluded an integrated study of a compact stellarator power plant, involving physics and engineering design optimization. Key considerations include the size core, access for maintenance, minimum distance required between plasma coil to provide acceptable shielding breeding. Our preferred core option in three-field-period configuration is dual-coolant (He + Pb-17Li) ferritic steel modular blanket concept coupled with Brayton cycle port-based maintenance scheme....
AbstractARIES-ACT2 is a conventional tokamak power plant conceptual design that uses dual-coolant lead-lithium (DCLL) blanket concept with RAFS (reduced-activation ferritic steel) first-wall (FW) and structure. The the first fully integrated study of DCLL in plant. major engineering efforts were to develop credible configuration can meet aggressive maintenance goals achieve high availability maintainability; tritium breeding requirements reasonable helium Pb-17Li cooling schemes remove...
A helium-cooled plate-type divertor design concept has being proposed within the framework of ARIES power plant study. W tiles are used as sacrificial armor, W-alloy main structural material and advanced ODS (oxide dispersion-strengthened) steel coolant manifold. An impinging jet cooling scheme is employed to enhance heat transfer characteristics in high flux zone. This paper describes optimization plate through parametric studies including thermo-fluid thermo-mechanical analyses.
The critical issue of divertor configuration for heat and particle flux control in a conceptual ARIES compact stellarator (CS) reactor is addressed. goal to determine location geometry with peak load not more than 10 MW/m2 CS equilibrium based on the be used NCSX experiment, optimized high beta (6.4%) designed low alpha-particle power loss fraction (≤5%). surface target has three components: thermal particles, lost energetic alphas, radiation from core scrape-off layer. first two components...
AbstractARIES-ACT1 is an advanced tokamak power plant conceptual design that utilizes SiC composite structural material in the blanket and PbLi as tritium breeder coolant. This concept represents evolutionary step from ARIES-AT, which has guided research programs for past decade. In conjunction with a helium Brayton cycle, high primary coolant outlet temperature allows thermal conversion efficiency of 58%. The self-cooled He-cooled W-alloy divertor provide ability to survive relatively...
AbstractARIES-ACT1 engineering design efforts were devoted to developing a credible configuration that allows for rapid removal of full-power core sectors followed by disassembly in hot cells during maintenance. The power evolved with the main objective achieving high performance while maintaining attractive features and configuration, maintenance, fabrication processes. To achieve availability maintainability fusion plant, components sector, including inboard outboard first wall...
ARIES-ACT1 is the latest in a series of tokamak power plant designs that capitalize on high-temperature capabilities and attractive safety environmental characteristics SiC composites coupled with self-cooled lead-lithium breeder. This combination offers both design simplicity high performance, capable operating at very coolant outlet temperature moderately high-power-density device. Blankets are supported within poloidally continuous He-cooled steel structural ring, which adds robustness...
This paper considers a combination of ARIES modular finger concept and design with helium channels in thick plate. Multiple-jet cooling at back side plasma facing surface is employed this concept. The subdivided into large number small hexagonal modules, similar to the EU Such modularization reduces thermal stresses allows therefore maximum heat flux 10 MW/m2 least. A solution has been found allowing brazing fingers made W-alloy directly W-plate, avoiding way connection dissimilar materials...
The ARIES-CS study focusing on the conceptual design and assessment of a compact stellarator power plant identified important advantages key issues associated with such design. coil configuration structural support approach represent challenges, final material choices affected by number geometry constraints. This paper describes analysis for magnets its structure. To meet aggressive cost assembly/maintenance goals, are designed as lifetime components. Due to very complex geometry, one goals...
As a part of ARIES-ACT research, we have been performing detailed re-examination requirements and design vacuum vessels for fusion power plants. This paper discusses structural analysis performed in support this examination. We parametric 3-dimensional finite element analyses ARIES-ACT-type vessels. The vessel structure is subjected to different types loads such as atmospheric pressure, weight the itself off-normal over-pressurization due leak core components, electromagnetic forces from...
AbstractARIES-ACT1 power plant has been designed and configured to allow for rapid removal of full core sectors followed by disassembly in hot cells during maintenance operation. To achieve high availability maintainablity a fusion plant, components sector, including inboard outboard FW/blankets, upper lower divertor, structural ring or temperature shield were integrated into one replacement unit minimize time comsuming handling inside plasma chamber. In this paper, the overall configuration...
The use of tungsten as a plasma-facing material necessitates transition joint to the structural primary coolant loop at some location in order transport heat exchanger. A critical issue joints is thermal expansion mismatch between materials, which can lead unacceptably high stresses. Detailed 2D and 3D analyses were performed study behavior from ferritic steel (FS) with an intermediate layer tantalum, located outside flux region. This paper describes results FEM including secondary stresses...
The current T-tube divertor design consists of modular helium cooled units. individual units consist a steel inner cartridge enclosed in tungsten alloy outer structure. On top the tube is layer pure armor. Past and analysis concept has shown that it can accommodate heat flux up to 10MW/m2. With recent concerns steady state or transient fluxes may be higher than this region, was modified so fluxes.
AbstractAs part of the ARIES-CS study, machine configuration design, including power core components and attachment, coil supporting structure, cryostats vacuum vessel, is developed in close integration with chosen port maintenance scheme. This paper summarizes major features design plant.
A modular dual coolant lead-lithium (DCLL) blanket concept has been selected as the reference design for ARIES-CS compact stellarator power plant study. The major characteristics of arrangement and core integration associated with maintenance scheme are summarized in this paper.
Previous conceptual design studies for liquid-metal (LM) cooled blankets of a fusion power plant often omit details the complete flow distribution network required to bring coolant into and out blanket, especially manifolding transition from small number feed pipes sometimes large parallel channels within actively heated part core. Manifolding can induce 3D MHD currents therefore dominate pressure distributions entire which is problematic designs with electrically insulated channels. Within...