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Status of the ARIES Program

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Presentation on theme: "Status of the ARIES Program"— Presentation transcript:

1 Status of the ARIES Program
Farrokh Najmabadi UC San Diego US/Japan Workshop on Power Plant Studies and Related Advanced Technologies 23-24 February 2010 US San Diego

2 Current ARIES Proposal (Starting Jan 2010)
Investigation edge plasma physics and plasma-material interaction, high heat flux components and off-normal events in a fusion power plant.

3 Background PMI and High-Heat Flux components as well as off-normal events are emerging as the most critical issues for fusion power. Considerable change in predictions of heat and particle fluxes in in-vessel components ARIES Designs were done in the context of the best available information at the time. ARIES-AT is ~10 years old. All of ARIES design will probably optimized differently. There is a considerable confusion re capability of various components to handle heat/particle fluxes, i.e., in many cases peak transient heat fluxes are compared with the steady-state heat-flux capabilities. An integrated solution should be found that does not transfer the problem to another system in the power plant.

4 Goals: Re-evaluate ARIES design with a strong emphasis on the current predictions for PMI/PFC issues. What would ARIES designs look like if we use current predictions on heat/particles fluxes? What would be the maximum fluxes that can be handled by in-vessel components in a power plant? Can the current physics predictions (ITER rules) be accommodated and/or new solutions have to be found? What level of off-normal events are acceptable in a commercial power plant? Do recent divertor proposals help reduce the gap and by how much? Are there any other opportunities for innovative solution to PMI/PFC issues?

5 How to Proceed? Frame the “parameter space for attractive power plants” by consider the four corners of parameter space: Use the system code aggressively to understand the trade-offs Update the previous work as much as possible: More embodiments can be considered for a given time.

6 Available design space is explored with the new ARIES systems code
ARIES-I Plasma Both advanced physics (advanced tokamaks) and advanced material (high-efficiency blanket) enlarge the design window ARIES-AT Plasma

7 To bridge the gap between achievable physics and engineering performance, advanced divertor concepts will be explored (with emphasis on Helium-Cooled W-alloy divertor designs) Temperature and stress limits are the reason for heat flux limits on plasma-facing components Advanced design concepts attempt to improve heat transfer (with acceptable pressure drop) and maintain stresses within allowable limits for materials in our portfolio Fabricability, maintainability and reliability are always at the heart of new design ideas ARIES is moving toward full time-dependent engineering analyses accounting for fabrication steps, normal and off-normal operating modes T-Tube divertor: ~1.5 cm dia. X 10 cm long Impinging-jet cooling Allowable heat flux>10 MW/m ~110,000 units for a power plant Plate-type divertor: 20 cm x 100 cm Impinging-jet cooling Allowable heat flux ~10 MW/m2 ~750 units for a power plant Combination of the plate and EU finger divertor Fingers for q>8 MW/m2 Plate for q<8 MW/m2 Increased design margin and number of finger units

8 Example Fluid-Thermal-Mechanical Coupled Analysis for the Two Zone Divertor Concept
High heat flux zone Heat transfer coefficient Coolant temperature

9 Experimental evaluation and validation of the thermal performance of gas-cooled divertor designs at Georgia Tech Leading He/W divertor designs rely on jet impingement cooling to achieve desired performance Goal is to accommodate heat fluxes of at least 10 MW/m2 Performance is “robust” with respect to manufacturing tolerances and variations in flow distribution Extremely high heat transfer coefficients (~50 kW/m2K) predicted by commercial CFD codes used for the design Such numerical predictions are experimentally validated

10 Pushing materials to their limits requires sophisticated nonlinear analysis of component responses
Traditional approach to stress analysis involves equilibrium elastic analysis and comparison with ASME code (3Sm limits) Non-linear materials responses, such as plastic deformation (yield) and creep allow materials to be pushed beyond 3Sm, BUT detailed analysis and validation is required Plasticity is a non-conservative, path-dependent phenomenon; the sequence in which loads are applied, and in which plastic responses occur, affects the final solution. Creep occurs as a result of long-term operation at high temperature, and as a result of irradiation Example analysis: Transition joints between W and steel are critical for the plate-type concept because thermal expansion of steel is ~3-4 times higher than W, causing high stresses during operation

11 We are exploring first wall concepts that can handle large transient events
Design goals are to accommodate a heat flux of 1 MW/m2 in a normal operation and up to 2 MW/m2 at transient events. Design concept is to embed a micro-brush like W-pins into a ODS plate to raise the effective conductivity of the first wall layer. W-pins ODS plate with holes FS channel

12 In Summary The ARIES Research is focusing on the investigation of edge plasma physics and plasma-material interaction, high heat flux components and off-normal events in a fusion power plant. What would be the maximum fluxes that can be handled by in-vessel components in a power plant? Can the current physics predictions be accommodated and/or new solutions have to be found? What level of off-normal events are acceptable in a commercial power plant? Are there any other opportunities for innovative solution to PMI/PFC issues? The new ARIES Proposal focuses on the critical scientific issues identified by FESAC and supports several trust areas identified by ReNew

13 Some ARIES Town Meetings
Date Location Subject Mar. 2-3, 1995 ANL ARIES Workshop on Liquid Target Divertors May 10, 1995 ARIES Town Meeting on Structural Materials Jan. 31, 1996 UCSD ARIES Town Meeting on Low Aspect Ratio Spherical Tokamaks June 19, 1997 UW ARIES Town Meeting on Designing with Brittle Materials May 6-7, 1998 ARIES Town Meeting on ST Physics Jan , 2000 ORNL International Town Meeting on SiC/SiC Design & Material Issues for Fusion Systems Mar. 6-7, 2001 Livermore ARIES Tritium Town Meeting May 5-6, 2003 ARIES Town Meeting on Liquid Wall Chamber Dynamics Sep , 2005 PPPL ARIES Compact Stellarator Physics Town Meeting Dec , 2008 International HHFC Workshop on Readiness to Proceed from Near Term Fusion Systems to Power Plants May 2010 Town Meeting Edge Physics Modeling and experimental validation for fusion power plants. (to be followed with a workshop)

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