Fusion Nuclear Science Facility (FNSF) low Q mission range & prerequisites options in associated research program for discussion and feedback

Transcription

1 Fusion Nuclear Science Facility (FNSF) low Q mission range & prerequisites options in associated research program for discussion and feedback Normal Plasma Aspect Ratio Embodiment: Fusion Development Facility (FDF) Martin Peng, ORNL FNST/PFC/MASCO Meetings August 2 6, 2010, UCLA Updated from discussions with: FNSF steering (advocacy) group FNST workshops in 8/08, 8/09 VLT in 4/10 ARIES PMI mtg & MASCO in 6/10 GA MIT ORNL conf. call in 6/10 Low Plasma Aspect Ratio Embodiment: Fusion Nuclear Science Facility (FNSF) Other Embodiments such as FNSF Pilot Plant?

2 New Approach led by Starting Quarterback from PPPL A Traditional Thinking: Extend from ReNeW and Greenwald reports; Address Plasma Dynamics & Control and Materials infusionenvironment ; Aim for Low Q, Low Cost, Low Risk, Complementary to and in Parallel with ITER Fluence: 1 MW-y/m 2 6 MW-y/m 2 6 MW-y/m 2 Pulse-length: Up to 2 wks Up to 2 wks 2 wks Duty factor: Up to 10% Up to 30% 30% Prereq- uisite R&D Accompanying Tokamaks Baseline Stretch Eng. Tech. R&D FNSF-LQ FNSF-AT Q= Q=5-10 p <ITER p >ITER CTF A (TBD) A (TBD) Q = 10 ITER Q = 5 Long-pulse ITER Basis for First DEMO 6-20 MW-y/m 2 Several months 50% 0.1 MW-y/m s 2.5% 0.3 MW-y/m s 6%

3 Low A Example: Conservative plasma parameters with R 0 = 1.3m, A = 1.7 to provide the needed fusion environment [Peng et al, Fusion Science and Technology 56 (2009) 957; Peng et al, FEC 2010, FTP/2 3Ra] Low A FNSF Normal A Examples also exist. [Stambaugh et al, EPS 2010, P2.110; Chan et al, FEC 2010, FTP/2 3Rb] Disruption minimized plasma: N 0.75 N no wall ; HH 1.25; q cyl 2xlimit; J avgtf 4 ka/cm 2 Plasma Pressure Fuel JET DD JET DT 2xJET 4xJET Pressure = B T2 T (T 2 %) Fusion gain Q W L (MW/m 2 ) Current, I p (MA) Field, B T (T) Safety factor, q cyl Toroidal beta, T (%) Normal beta, N Avg density, n e (10 20 /m 3 ) Avg ion T i (kev) Avg electron T e (kev) BS current fraction NBIH&CD power (MW) Fusion power (MW) NBI energy to core (kv)

4 Example FNSF mission: to provide, in parallel with ITER, a scientific users facility for Materials in Fusion Environment research to develop basis for Demo, in concert with Burning Plasma Dynamics & Control research Research ) cs & Control R pressure p asma Dynamic asing plasma p 1: Burning pla (Increa G#1 Future engineering & technology testing to develop and demonstrate Demo qualified internals based on the new Fusion Energy Sciences knowledge. Present research to test, discover, understand, and innovate in Fusion Energy Sciences (making progress in Goals #1 and #2 in concert) JET DT DD S/C FNSF DD Toks. 1xJET p FNSF DT 1xJET p ITER BP 3xJET p FDF DT DT 2xJET p FNSF DT 2xJET p FDF I 4xJET p CTF FDF AT 6xJET p FDF dpa 8xJET p FNSF DT 4xJET p FNSF AT 6xJET p FNSF dpa 8xJET p DEMO, Pilot Plant (Q=20 30) G#2: Materials in Fusion Environment Research (PSI, Nuclear Effects, Harnessing Fusion Power) (Increasing fusion neutron flux ) n Transitio on etch Mission Q = 5 10) Stre (Q Baseline Mis ssion (Q = )

5 Configuration for Full Modularization of the FNSF Internals to allow extensive Remote Handling and upgradability will improve performance risk ratios All internal or activated components are included. All device structures behind the internals are shielded to ~1% of time accumulated radiation dose on the internals.

6 Hot cells for preps & repair, and for fusion materials R&D Remote handling equipment for hot cells to support operations and enable fusion materials research (see, animation of concept) Vertical cask docking port Midplane cask docking port Vertical port handling cask (18 meters) Hot Cell Laboratories servomanipulator Mid plane port assembly handling cask

7 FSNF Working Groups of Expert Stakeholders in Key Topical Areas Should Be Formed and Engaged to Assess and Delineate Prerequisite R&D, Risks and Integrated R&D for the FNSF Configuration and Performance Ranges Configuration and Performance Ranges Affects Prerequisites & Risks: Normal vs. Small Aspect Ratio; Conservative vs. Aggressive Physics; Baseline vs. Stretch Missions; Tokamak vs. CS vs. GDT; FES only vs. broader federal science facility, etc. Fusion Plasma Dynamics Plasma Enabler & Control Plasma Facing Component Fusion Resilient Magnets Nuclear Effects on Materials Remote Handling Tritium Cycle Power Extraction Measurement Science Modeling, Computation & Validation C-Mod DIII-D NSTX Sliding Joint HFIR Production PMTF-1200 Burning Plasma Burning Plasma EAST KSTAR JT-60SA ITER Project Ion Beams? Modular Components Extraction MTOR Plasma Material H&CD Single-Turn Fueling & SNS Pumping Control Systems RH systems, Maintenance Facility Processing Liquid Metal Breeder Blanket Plasma Material Material Irradiation Surface PISCES-B New Linear Plasma Advanced Analysis Material Test Stand? Designs Multi-Turn IFMIF New Fusion Materials Hot-Cell Laboratory? Control & Safety Solid Breeder Blanket Nuclear Instrumentation & Control Liquid Metal MHD ITER TBM Neutron Transport

8 In the space of FES Goals #1 and #2, FNSF as a Science Users Facility enables effective management of performance cost risk FNSF+FNSP to test, discover, understand, and innovate to develop basis for Demo FNSF programmatic start strategy: Conservative reliable toroidal plasma performance (JET DD and DT level, low Q, high q). Conservative reliable materials, engineering and technology performance. Achieve progress in the emerging Goal #1 and Goal #2 research in concert both or none. Prerequisite R&D: to ensure successful start of this fusion environment, What steady state plasma conditions to avoid or minimize plasma induced disruptions? What materials should be used in initial internal components and the shielded structures? What PFC divertor approaches to enable the start of the initial research operations? What initial blanket, tritium, power extraction designs and capabilities? Cost effective upgradability: H D DT conservative DT AT, accumulating dpa Fully modular internals, extensive remote handling, and hot cell facilities for preps p and repair. Standardized interface for all internal modules, enabling competitive designs. Multiple backup modules ready in waiting, to ensure high utilization. Tests in H allow full hands on; in D allow limited hands on, before DT requiring full remote. Remote handled Fusion Materials Hot Cell Laboratories, for new fusion materials science. Shielded support structures (to ~10 2 dose) allow up to 100 dpa time integrated internal dose. Maximize potential progress in research for both Goal #1 and Goal #2 in concert. Recommended roles for research users of a Fusion Nuclear Science Program (FNSP): Provide conservative initialchoices for materials, internalmodules modules, and plasmaoperation scenarios to start FNSF research program. Use FNSF to obtain critical new database for DEMO, in Goals #1 and #2 in concert. FNSF enabled to support FNSP research in stages.