engineering overview of aries act1 n.
Download
Skip this Video
Loading SlideShow in 5 Seconds..
Engineering Overview of ARIES-ACT1 PowerPoint Presentation
Download Presentation
Engineering Overview of ARIES-ACT1

Loading in 2 Seconds...

  share
play fullscreen
1 / 19
kshort

Engineering Overview of ARIES-ACT1 - PowerPoint PPT Presentation

0 Views
Download Presentation
Engineering Overview of ARIES-ACT1
An Image/Link below is provided (as is) to download presentation

Download Policy: Content on the Website is provided to you AS IS for your information and personal use and may not be sold / licensed / shared on other websites without getting consent from its author. While downloading, if for some reason you are not able to download a presentation, the publisher may have deleted the file from their server.

- - - - - - - - - - - - - - - - - - - - - - - - - - - E N D - - - - - - - - - - - - - - - - - - - - - - - - - - -
Presentation Transcript

  1. Engineering Overview of ARIES-ACT1 UC San Diego UW Madison GIT ARIES PPPL INEL M. S. Tillack, X. R. Wang and the ARIES Team Boeing GA Japan/US Workshop on Power Plant Studies and Advanced Technologies 26-27 February 2013

  2. The ACT1 power core evolved from ARIES-AT (advanced physics and advanced technology) Similarities High performance plasma (bN~5-6) SiC composite breeding blanket with PbLi at To~1000 C Brayton power cycle with h~58% Differences • Machine parameters, e.g. R=6.25 vs. 5.5 m, higher qdiv • Power core design choices • He-cooled W divertor • Steel structural ring • Simplified blanket coolant paths • Simplified vacuum vessel with external LT shield

  3. Main parameters and configuration

  4. The power core replacement unit is self-supporting and maintained as a single unit Internal parts are attached to a continuous steel ring. All coolant access pipes are located at the bottom. Sectors are moved on rails through large maintenance ports and transported in casks. Immediate replacement with fresh sectors minimizes down time. Main penalty is larger coils.

  5. Sector alignment and maintainence are performed using a rail system • The power core sectors are supported by T-shaped extensions on the bottom of the structural ring that fit into rails. • Pistons are inserted during maintenance for vertical and horizontal alignment. Ample space within the rails allows alignment of the sector in all directions. • After alignment, the grooves are filled with a liquid metal (possibly a Cu-alloy) and fixed in position by freezing. The pistons can then be withdrawn.

  6. Liquid metal manifolds are designed to minimize MHD effects Option 1: Y-network manifold Option 2: Bolted connector plates

  7. The vacuum vessel is designed to operate at high temperature • 350˚C operating temperature minimizes tritium inventory. • Low-activation 3Cr-3WV bainitic steel • Lower activation than 316SS • No post-weld heat treatment • Ample volume to accommodate He LOCA • No need to support other components. • 10 cm total thickness, including embedded He cooling channels.

  8. A He-cooled W-alloy divertor was chosen to allow high temperature and heat flux capability Jet cooling has been shown to accommodate up to 14 MW/m2. Better edge physics needed to predict heat flux accurately. W-alloy development is needed.

  9. The integrated plate-finger concept provides good performance with mimimum complexity (results for 600/700˚C He inlet/outlet temperature) ARIES-AT heat flux profile q<10 MW/m2 q>10 MW/m2

  10. The breeding blanket uses annular pipes to maximize coolant outlet temperature

  11. Temperatures were computed using laminar heat transfer with variable flow FW and SW flows are mixed to create uniform central duct inlet temperature Effect of curvature included

  12. Structures remain within their limits, with a modest variation from front to back ˚C ˚C • Results shown for outboard blanket-I • 10 m length from bottom to top • Radial and axial variations in volumetric heating • Constant surface heat flux, constant properties

  13. Thermal stresses satisfy requirements Local thermal stress =~91 MPa Pressure stress<~50 MPa Total stresses=~141 MPa Thermal stress <60 MPa Local pressure stress=~88 MPa Total stresses=~148 MPa • Location is near the IB blanket bottom • 3Sm rules for metal pressure vessels do not apply: • Limit of 190 MPa combined primary and secondary stress(Raffray et al, “Design and material issues for SiCf/SiC-based fusion power cores,” Fusion Eng. Design 55 (2001) 55-95.) • We allocated 100 MPa for primary and 90 MPa thermal stress.

  14. Evaluation of MHD pressure drops FW core inertia gravity wall shear 3D MHD ru2 rgL suB2L/Ha kN (ru2)/2 160,000 8x105 190,000 3x106 100 8x105 475 7x105 u conservative L dissipative g A where k depends on wall conductance, pipe shape (e.g. circular or rectangular) and other details.

  15. Heat exchanger Pressures and pressure drops for the ARIES-ACT1 IB blanket Dp = 0.25 MPa 0.25 (outboard Dpmhd will be lower) p > 0 4 m (0.4 MPa) Dptop = 0.1 MPa 0.95 0.85 Dpbulk = 0 8 m (0.8 MPa) DpFW = 0.2 MPa 1.65 1.95 Dpout = 0.2 MPa Dpin = 0.45 MPa 2.4 4 m (0.4 MPa) 1.45 1.2 MPa pump 1.6 2.8 1.85 1.85

  16. Primary stress analysis determined module dimensions and fabrication requirements First wall

  17. Power flows and bulk coolant temperatures in ARIES ACT1 1030 C hot h=58% 1000 C 1519 MW 5 MW 733 C PbLi HX FW blanket cold 303 MW 703 C primary side divertors 800 C hot pump heat pump heat 700 C He HX 10 MW 692 C 600 C 217 MW hot shields 650 C cold to He HX recuperator 600 C secondary side from PbLi HX Heat sink 1000 C turbine

  18. Our Brayton cycle achieves ~58% efficiency • Matching all of the coolant temperatures is needed. • hrecuperator==96%, hturbine=92% • Result depends on inlet temperature as well as outlet; >57% could be achieved with 550˚C inlet.

  19. ARIES-ACT1 issues are well known, and the subject of ongoing R&D • Characterization of steady and transient surface heat loads. • MHD effects on flow and heat transfer. • Fabrication, assembly and joining of complex structures made of SiC composites, tungsten alloys, and low activation ferritic steels. • Failure modes and rates: Mechanical behavior of steel, W and SiC structures, including fracture mechanics, creep/fatigue, and irradiation effects. • Upper and lower temperature limits of W alloys and advanced ferritic steels. • Fluence lifetime of components under anticipated loading conditions. • Erosion of plasma-facing components. • Tritium containment and control.