April 27-28, 2006/ARR 1 Finalizing ARIES-CS Power Core Engineering Presented by A. René Raffray University of California, San Diego ARIES Meeting UW, Madison.

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CERAMIC BREEDER BLANKET FOR ARIES-CS
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CERAMIC BREEDER BLANKET FOR ARIES-CS
Presented by A. R. Raffray University of Wisconsin, Madison
University of California in San Diego
Status of ARIES-CS Power Core Engineering
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Presentation transcript:

April 27-28, 2006/ARR 1 Finalizing ARIES-CS Power Core Engineering Presented by A. René Raffray University of California, San Diego ARIES Meeting UW, Madison April 27-28, 2006

April 27-28, 2006/ARR 2 Choose a Set of Machine Parameters to Perform Final Design and Analysis of Power Core Components From Jim’s and Laila’s presentations, the case with R=7.5 m would probably be the one with the lowest COE satisfying all our constraints However, we are using 90% 6 Li enrichment and have no active knob for increasing TBR if required during operation. We might have some margin with the 15% divertor coverage assumption. Should we choose the case with R=7.75 m with a somewhat lower 6 Li enrichment and slightly higher margin with respect to our constraints and requirements? ….and the winner is: R=7.5 m? NO, it is R = 7.75 m

April 27-28, 2006/ARR 3 We Have Made Good Progress on the Design and Analysis of Power Core Components, but There are Still a Few Areas Where We Need To Fill the Gap Divertor and Prompt Alpha Accommodation -Difficulty in obtaining results to define location and heat flux on divertor and regions that would need to accommodate the alpha loss. Continue our effort there (T.K. Mau) -In the mean time, we need to define zero-order parameters for our analysis -Suggestion: scale roughly from W7X divertor work and from our work to-date to locate divertor plates (for Laila’s analysis and also to provide a better estimate of the coverage fraction) (T. K. Mau) -For now, maintain the assumption of 15% coverage for divertor + alpha accommodation? -Need to agree on a core radiation fraction, a local divertor edge radiation fraction for a reasonable anticipated peaking factor on divertor (and for alpha deposition) and for a max. heat flux of 10 MW/m 2 (J. Lyon would need this also) -But we need some physics basis for the assumed numbers (T.K. Mau, J. Lyon)

April 27-28, 2006/ARR 4 We Have Made Good Progress on the Design and Analysis of Power Core Components, but There are Still a Few Areas Where We Need To Fill the Gap (cont.) Coil and Structure Analysis -Great that we can compare 2-D shell model results with 3-D solid model results for example case so that we can apply them to scale other shell model results -Need to analyze effect of penetration and rib requirement (X. Wang) -Zero-order estimate of structure thickness variation based on stress profile (X. Wang) -Need to choose between Incoloy and Japanese material (L. Bromberg) CAD Drawing -Need to update CAD drawings for our final design choices (no bucking cylinder) (X. Wang) -Do we need control coils and if so where are they located; need to show them on our CAD drawings (L-P. Ku) Blanket -Perform stress analysis on final design -First wall heat flux distribution (J. Lyon, L-P Ku) System runs -For both blanket designs (reference and advanced) (J. Lyon) -Availability assessment to back up our number (L. Waganer) Safety analysis -For both blanket designs? (B. Merrill)

April 27-28, 2006/ARR 5 Example List of Papers to be Submitted to 17 th TOFE, Albuquerque, Nov 13-15, 2006 (abstracts due by June 9, 2006) Overall paper (Farrokh) Engineering paper (Rene) Physics configuration (Long-Poe) System (Jim) Neutronics analysis (Laila, UW) -Neutronics performance -Waste management -Radial build Maintenance (Xueren/Siegfried) Hot core design (Xueren/Siegfried) Coil design and analysis (Xueren/Rene) Coil material choice (Leslie) Out of reactor layout and maintenance considerations (Les) Safety analysis (Brad) Divertor heat loads (T.K) Divertor T/H experiments (Said)

April 27-28, 2006/ARR 6 17th TOFE Technical Program Tuesday, November 14, 2006 Tuesday Morning - 8:00 to 10:00 (3 || sessions, 6 talks per session, 20 min each) Power Plant Studies ITER Test Blanket Modules Non-Electric Applications Coffee Break - 10:00 to 10:30 AM Tuesday Morning - 10:30-12 AM (3 || sessions, 5 talks per session, 18 min each) ARIES Compact Stellarator Target Development and IFE Technology Latest Technology and Tritium System Lunch :30 PM Currently an ARIES-CS session is scheduled at the 17 th TOFE (need to check with C. Olson about this)