FIFTH IAEA DEMO PROGRAMME WORKSHOP

Transcription

1 Fusion reactor graphic by HANS-ULRICH OSTERWALDER / Science Photo Library / picturedesk.com Programme FIFTH IAEA DEMO PROGRAMME WORKSHOP 7 10 May 2018 National Fusion Research Institute Daejeon, Republic of Korea

2 Monday, 7 May Session Welcome and Opening Address S. M. Gonzalez de Vicente, E. Surrey, K. Kim Plasma Control Chair: WOLFGANG BIEL WOLFGANG BIEL Introduction and overview of Plasma Control WOLFGANG TREUTTERER ITER control system FILIP JANKY Kinetic control Lunch Break SANG-HEE HAN Equilibrium Control EUGENIO SCHUSTER Advanced control HIROSHI YAMADA Stellarator Control Discussion Special Topic Adjourn KEEMAN KIM Korean DEMO programme Tuesday, 8 May 2018 Session Remote Maintenance Chair: OLIVER CROFTS OLIVER CROFTS Introduction and overview ERIC VILLEDIEU Tokamak architecture for practical Remote Maintenance Poster Session 1

3 SATOSHI KAKUDATE DEMO service joining technology Lunch Break Discussion Special Topic Adjourn NICK SYKES The maintenance support facility GARY REED Safety implications for Remote Maintenance Poster Session 1 YONG CHEN Intelligent maintenance for fusion reactors AKIRA SAKASAI JT60-SA, Status and Scientific Objectives Wednesday, 9 May 2018 Session Magnets Chair: PIERLUIGI BRUZZONE PIERLUIGI BRUZZONE Introduction and Overview NAGATO YANAGI Demountable coils for fusion Poster Session 2 THOMAS RUMMEL Lesson learned during the design, construction and commissioning of the magnet system for W7-X Lunch Break PETER TITUS Structural issues for large fusion magnets SOREN PRESTEMON Quench protection for large magnets Poster Session 2

4 Discussion Special Topic Adjourn KIYOKAZU SATO Manufacturing aspects for large fusion magnets CHARLES KESSEL Integrated Assessment of Liquid Metals as Plasma Facing Components on the First Wall and Divertor TCP MEMBERS AND CO-CHAIRS TPC Meeting Topic summaries Thursday, 10 May KSTAR Tour Special Topic Topic Summaries Discussion Workshop Chair Remarks E. SURREY Closing Remarks MOHAMED ABDOU US/UCLA-EUROfusion collaboration W. BEIL, O. CROFTS, P. BRUZZONE Topic Summaries S. M. GONZALEZ DE VICENTE End of Meeting TCP MEETING

5 List of Posters Number P1 P2 P3 P4 P5 P6 P7 P8 P9 P10 P11 P12 P13 Author & Title POSTER SESSION 1: TUESDAY, 8 MAY 2018 AHMAD Z. Poloidal Field Coils Studies Using 2G-HTS Tape for Demo BRUZZONE P. A cost effective design for the Toroidal Field Coils of EUROfusion DEMO LONG P. Virtual Reality based Maintenance Simulation and Dose Assessment for Fusion Facility HELLER R. The HTS CrossConductor as a potential candidate for a fusion magnet LIU L. The time-dependent modeling of CFETR baseline steady-state operations PRASAD U. Fusion relevant superconductor and magnet development activities at IPR SAKAMOTO Y. Operation scenario development and control issues on DEMO POSTER SESSION 2: WEDNESDAY, 9 MAY 2018 SHI SH. Design and Implementation of a Manipulator System for Remote Maintenance of EAST In-vessel Components SOMBOONKITTICHAI N. Numerical Study on Power Degradation by ITER-like Metallic Dust in DEMO SONG X.M. A plasma scenario design tool on HL-2M UTOH H. Evaluation of Magnetic Error Field based on Accuracy of Superconducting Magnets in DEMO reactor WADE M.R. Comparative Analysis of High-Critical-Temperature Superconducting Magnets on Future Reactor Designs ELDON D. Magnetic configuration and control considerations for DEMO stability and power handling

6 TOPICS 1. MAGNETS Magnet technology for magnetic confinement fusion has advanced to the point where several tokamaks and stellarators are now operating with superconducting magnets. The construction of ITER is taking the technology of fusion magnets based on low-temperature superconducting (LTS) magnets to an unprecedented scale. Already, high-temperature superconductors (HTS) are being considered for use in next-step fusion devices. This session will focus on the possibilities for further advances in magnet technology, including but not limited to HTS, which can benefit the fusion programme. Comparisons with present technology will include design implications and limitations, manufacturing capability and capacity, economics, and safety implications. Topic Chair: Pierluigi Bruzzone 2. CONTROL OF DEMO PLASMAS Previous DEMO Programme Workshop (DPW) reviews of plasma scenarios and their control requirements have stressed the need for robust control close to operational boundaries. Control in DEMO will have to ensure maximum availability at the chosen operating point, so it will potentially be quite different from present day devices which place greater emphasis on flexibility. The DPW 5 session on plasma control will include: (i) a review of advanced control techniques, focusing on associated requirements for sensors and actuators; and (ii) plasma scenario requirements compatible with the limitations of diagnostics and actuators under DEMO conditions. The advanced control techniques will include nonlinear controllers and state-observers. Model-based versus empirical approaches will be compared. Special emphasis will be placed on minimizing the disruptivity and identifying gaps and strategies to cope with unpredictable or rapid events. These subjects are of great importance for ITER as well, and hence a strong link to the developments for ITER in this field will be made. Topic Chair: Wolfgang Biel 3. REMOTE MAINTENANCE AND PLANT LOGISTICS The remote maintenance (RM) requirements of DEMO operation are major drivers of component design and machine configuration and operation. Ensuring compatibility with access and manoeuvring requirements whilst simultaneously satisfying safety constraints will significantly impact the design of the entire facility with considerable bearing on cost. This session will include comparison of different RM schemes (e.g. vertical and horizontal), limitations that impact design (e.g. lift weight), operations in high radiation environments (e.g. sensors, virtual modelling), hot cell requirements, virtual engineering and scaled prototyping. Topic Chair: Oliver Crofts 4. SPECIAL TOPICS Korean DEMO programme JT60-SA, Status and Sciebtific Objectives Integrated Assessment of Liquid Metals as Plasma Facing Components on the First Wall and Divertor US/UCLA-EUROfusion collaboration