Page 1 of 11 An approach for the analysis of R&D needs and facilities for fusion energy ARIES “Next Step” Planning Meeting 3 April 2007 M. S. Tillack ?

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Presentation transcript:

page 1 of 11 An approach for the analysis of R&D needs and facilities for fusion energy ARIES “Next Step” Planning Meeting 3 April 2007 M. S. Tillack ?

page 2 of 11 Our external advisory committee will help us define broad R&D requirements for the commercialization of fusion Customer-derived requirements for a power plant (Starlite)  No public evacuation plan  No geological waste  No disturbance of public  No abnormal risk to workers  Closed tritium fuel cycle on site  Ability to operate at partial load  Ability to maintain power core  < 0.1 major unscheduled shut-down/yr  Competitive COE Customer-derived R&D needs  Demonstrate operability of the tokamak and power systems  Demonstrate control of key parameters  Demonstrate power handling capability, electricity generation  Demonstrate worker safety under normal and off-normal conditions  Demonstrate a closed fuel cycle and ability to manipulate breeding  Demonstrate remote maintenance

page 3 of 11 How will we translate advisory committee recommendations into design requirements and conceptual design priorities? Customer Needs Mission Present Database Requirements Reactor Conceptual Design Issues & R&D Needs R&D Implementation The Starlite Methodology is still relevant, but needs to be applied to experimental devices

page 4 of 11 For a power plant operator (the customer), the focus will be on integrated rather than component issues Plasma Blankets Divertors Magnets Vacuum vessel Power management Reactor control Fuel management Maintenance Safety Waste Our work should adopt a more “holistic” approach

page 5 of 11 Examples of integrated issues for system studies of experimental power reactors Thermal power management: Demonstrate in-vessel power and particle handling, extraction of power core high-grade heat, nuclear performance of ancillary equipment (rf, magnets, etc. ) Fuel management: Demonstrate “birth to death” tritium management in a closed loop with self-sufficient breeding. Safety: Demonstrate public and worker safety of the integral facility, capturing system to system interactions. Plant operations: Establish the operability of a fusion energy facility, plasma control, reliability of components, inspectability and maintainability of a power plant relevant tokamak. Flexibility: Explore alternative operating modes and power core technologies with high duty cycle, but flexible operations.

page 6 of 11 An experimental reactor design will require more emphasis on operational concerns and demonstration of the achievement of goals E.g., Diagnosis and monitoring of plasma and plant conditions  Less than a tokamak experiment, more than a power plant Control (variation) of key parameters Transient response (partial power, power fluctuations, accelerated breeding, …) System interfaces, interactions and interdependencies Previous ARIES studies tended to emphasize an optimum baseline “equilibrium” point. In this study, we want to explore sensitivities, interdependencies, transients, etc.

page 7 of 11 Thermal power management: Demonstrate in-vessel power and particle handling, extraction of power core high-grade heat, nuclear performance of ancillary equipment (rf, magnets, etc.) Example: 1-f rad,div P fusion PnPn PP Divertor First wall, PFC’s P rad,chamb P div P cond P rad,div f rad,core 1-f rad,core f rad,div Blanket CoolingCooling Requires e.g. controlling and tracking all power flows, measuring stresses and temperatures, extracting materials coupons, post-test examination, … Can we study these with a combined system code w/physics & engineering? Plasma engineering

page 8 of 11 Fuel management: Demonstrate “birth to death” tritium management in a closed loop with self-sufficient breeding. inventory pumps breeder coolant breeder processing coolant processing vacuum processing fueling D+T D+T+  n T Fuel processing Example:

page 9 of 11 Do we want this? (C. Gentile, HAPL presentation, 9 Aug 2006)

page 10 of 11 A design requirements document is the first step toward an experimental fusion power reactor ARIES CTF/ FDF/ EPR/ TNS/ FED/ etc. This study is timely, and could be the precursor for a real facility

page 11 of 11 ITER/ FIRE ARIES “next step” Starlite