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ARIES Documents -- Meetings Archive

ARIES Conference Call, 17 February 2009, Revision A

Documented by L. Waganer

(ANL) -
(Boeing) Waganer, Weaver
(DOE) -
(FPA) -
(FZK) -
(GT) Abdel-Khalik, Yoda
(PPPL) Kessell, Meade
(UCSD) Dragojlovic, Malang, Raffray, Tillack, Wang
(UW) El-Guebaly


The next ARIES project meeting is to be held at the University of Wisconsin, Madison on April 23rd and the morning of April 24th. Laila El-Guebaly has secured a room and is making arrangements with the hotels. Please upload your presentation to the UW-M web site provided by Laila. If you cannot attend and wish to have phone access, please inform Laila.

The next project phone call will be on March 11 (Wednesday) and will focus on the progress on the ReNeW panels.

The US/Japan workshop will be held March 16-18, 2009 in Tokyo with participation of a few members of the ARIES team (Farrokh, Rene, and Laila).

Support of the ReNeW Workshops

Rene Raffray said that the Harnessing Fusion Power (HFP) and Plasma Materials Interface (PMI) themes were having overlapping workshop sessions at UCLA during the week of March 2-6. Wayne Meier is the HFP theme Chair and Rene is the co-Chair. ARIES has a good representation in this theme as well as in the other themes. Rene discussed the purpose of the workshop and the expected content of related white papers, presentations, and workshop results in terms of recommend research thrusts to advance the science and technology basis from ITER toward Demo. Mark Tillack will present the concept and utilization of Technology Readiness Levels (TRL) as applied to fusion R&D. Laila will present the new scheme to manage fusion activated materials along with the need for online adjustment of breeding. Les will give a talk on RAMI's importance to fusion.

Dale Meade mentioned that he is serving on two theme areas, Burning Plasma State in ITER and High Performance Steady-State Burning Plasmas. The panels in these themes are working to extend the Greenwald Panel issues analysis, quantify the gaps to DEMO, and identify research thrusts to fill these gaps. Chuck Kessel and Farrokh Najmabadi are also on the Theme II High Performance Steady-State Burning Plasma Integration sub-panel which is looking at which issues need to be addressed in an integrated manner. From the plasma standpoint, they are looking at Demo solutions ranging from ARIES-I to ARIES-AT.

Technical and Engineering Progress

Said Abdel-Khalik said the Georgia Tech team is fabricating a new divertor concept prototype for the helium cooled plate approach.

Laila El-Guebaly has been assessing the neutron streaming between sectors of the tokamak when they are designed with sector maintenance (e.g., ARIES-AT). The question arose in the RAMI ReNeW panel and Les Waganer asked Laila for more details, if available. Laila has done some additional assessment and will provide results at the April 09 meeting. Dale Meade mentioned that ITER has also addressed this issue. Laila assessed similar streaming problems for ITER in the early 1990s during the CDA phase. Recently, T. Bohm (UW) performed streaming analysis for the latest ITER assembly gaps and presented the results at the 18th TOFE in Sept 2008.

Laila has been evaluating the neutronic changes to the radial builds necessary to incorporate the DCLL blanket concept into a geometry similar to ARIES-AT. She presented the latest scoping assessment at the Jan-09 project meeting and has transmitted the information to Zoran for analysis. Siegfried Malang believes there has to be a detailed design modification before a meaningful comparison can be accomplished between the two different blanket concepts.

Mark Tillack noted that Spain also has begun a program to assess and develop a DCLL blanket. It is hoped that ARIES and Siegfried would receive credit on this technology.

Zoran Dragojlovic has been finalizing the ARIES Systems Code by incorporating the DCLL blanket and radial configuration provided by Laila. The revised geometry package is finished and it has been validated against ARIES-AT geometry. There had been some problems with the divertor geometry, pumping power, and power flows and all of these have been corrected. He has also been refining the parameter search routine to provide smoothed graphical results in the areas of interest.

Chuck Kessel noted that there has been increased concern about the ability of high performance plasmas to operate without major disruptions and high energy ELM discharges. Fast acting control coils integrated into the power core may alleviate the problem and operating away from the regions known to product discharges may prevent major discharges. ITER will provide useful data regarding this issue.

Xueren Wang has been analyzing the T-tube concept for the boundary conditions of ARIES-AT, characterized by a volumetric heat generation about one third of the value in ARIES-CS and an armor thickness of 5 mm. The divertor thermal-hydraulic analysis assumes a helium coolant pressure of 10 MPa. The resultant pumping power is about 5-6 percent of the thermal power. The maximum structural temperature is 1240°C as compared to the design limit of 1300°C.

Advisory Panel Utilization and Make-Up

Dale Meade has been assessing the utilization of an ARIES advisory panel, key questions that ARIES would like advice on and has proposed some people for the committee.