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Preliminary Conceptual Design Study of K-DEMO

Preliminary Conceptual Design Study of K-DEMO. Japan-US Workshop February 26 th , 2013 Advanced Project Division National Fusion Research Institute kkeeman@nfri.re.kr. Introduction. Mid-Entry Strategy in 1995. Conventional Device (Cu) Superconducting Device. DEMO. ITER. 1GW. JET.

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Preliminary Conceptual Design Study of K-DEMO

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  1. Preliminary Conceptual Design Study of K-DEMO Japan-US Workshop February 26th, 2013 Advanced Project Division National Fusion Research Institute kkeeman@nfri.re.kr

  2. Introduction

  3. Mid-Entry Strategy in 1995 Conventional Device (Cu) Superconducting Device DEMO ITER 1GW JET KSTAR TFTR JT-60U 1MW JET TFTR JET/TFTR Fusion Power 1KW DIII-D PDX SC Device DIII PLT ALCATOR C 1W T-3 KAIST-T (1968) KT-1 ATC SNUT-79 ALCATOR A 1965 1970 1975 1980 1985 1990 1995 2000 2005 2010 2015 2020 2040 Year 3

  4. KSTAR Superconducting Tokamak

  5. KSTAR Device for 2012 Campaign 2* ECE-I + MIR (POSTECH, UCD) VUV (ITER KO) FIR Thomson, 5 J, 100Hz (JAEA, NIFS) Reflectometer BES (8X8) (RMKI) Image Bolometer (NIFS) Div. IRTV NBI-1 2nd 100 keV, 2 MW, 10 s RMP PS 4 kA/t(n=1, 2) MD, Probes Da, VS, Filterscope(ORNL) XICS, CES (NIFS), ECE (KAERI, NIFS) BES (RMKI), CI/2D MSE (ANU), Interferometer, Bolometer (NIFS) SXR (KAIST), XPH (KAIST) Fast ion loss, Neutron (Hanyang U, ITER KO) • NBI-1 1st • 100 keV, 1.5 MW, 10 s • (KAERI, JAEA) ECH (170 GHz) 0.7 MW, cw (JAEA, PPPL) • ICRF • 30-60 MHz, • 1 MW, 1 s • (KAERI) ECH 84 GHz / 110 GHz 0.3 MW, 2 s (POSTECH, GA) LHCD 5 GHz, 0.5 MW, 1 s

  6. KSTAR In-vessel Control Coil System (3-D) • Modular 3D field coils (3 poloidal x 4 toroidal) • all internal and segmented with saddle loop configurations • 8 conductors in each coil • Control capability : vertical control, radial control, error correction, RMP, RWM • Wide spectra of Resonance Magnetic Perturbations (RMP) are possible • n=1 RMP (phase angles : +90, -90, 180, 0) and n=2 RMP (even or odd parity) n=1, +90 phase n=1, 0 phase  + + - - + + - - top top n=2, even parity - + + - + + - - mid mid + + - + - top - - + + + + - - bot bot - + - + mid  + - + - bot BP n=2, odd parity + - + - top mid - + - + bot Schematics of IVCC and its conductor

  7. βN-limit and ELM Suppression • KSTAR reachedβN〉2.5 and βN/li〉 4.0 • “no-wall limit” in H-mode Operation • ELM suppressed by n=1 RMP • (Ip = 600 kA, BT=1.6~2.3T) # 6123 Hα/ RMP 2012 New Data 2.7s 3.4s 4.3s

  8. Fusion Energy Development Promotion Law (FEDPL) • To establish a long-term and sustainable legal framework for fusion energy development phases. • Topromote industries and instituteswhich participating the fusion energy development by supports and benefit. • Thefirst country in the worldprepared a legal foundation in fusion energy development. • History of the FEDPL • 1995. 12 : National Fusion R&D Master Plan • 2005. 12 : National Fusion Energy Development Plan • 2007. 3 : Fusion Energy Development Promotion Law • 2007. 4 : Ratification of ITER Implementation Agreement • 2007. 8 : Framework Plan of Fusion Energy Development • (The first 5-Year Plan) • 2012. 1 : The 2nd5-year plan has begun

  9. Vision and Goal of Fusion Energy Development Policy Vision Secure sustainable new energy source by technological development and the commercialization of fusion energy Phase Phase 1 (’07~’11) Phase 2 (’12~’21) Phase 3 (’22~’36) Policy Goal Establishment of a foundation for fusion energy development Development of core technology for DEMO Construction of DEMO by acquiring construction capability of fusion power plants Basic Directions • Acquisition of operating technology for the KSTAR • Participation in the international joint construction of ITER • Establishment of a system for the development of fusion reactor engineering technology • High-performance plasma operation in KSTAR for preparations for the ITER • Completion of ITER and acquisition of core technology • Development of core technology for the design of DEMO • DEMO design, construction, and demonstration of electricity production • Undertaking of a key role in ITER operations • Completion of reactor core and system design of the fusion power reactor • Commercialization of fusion technology Basic Promotion Plan Basic Promotion Plan 1 (’07~‘11) Basic Promotion Plan 2 (‘12~‘16) Basic Promotion Plan 3 (‘17~‘21) Basic promotion plan 4(‘22~‘26) Basic promotion plan 5 (‘27~‘31) Basic promotion plan 6(‘32~‘36) Policy Goal for Plan-2 R&D for DEMO Technology based on KSTAR andITER Primary Strategy for Plan-2 • Attainment of KSTAR high-performance plasma anddevelopment of DEMO basic technology • Basic research in fusion and cultivation of man power • International cooperation and improvement of status in ITER operations • Commercialization of fusion/plasma technology and promotion of social acceptance

  10. Korean Fusion Energy Development Roadmap “Key Milestones” DEMO Final Design & Constr. Start DEMO R&D Launch & CDA Pre-Conceptual Design Study DEMO EDA Start DEMO Phase-1 Construction Finish 10

  11. K-DEMO Tokamak Design

  12. General Requirement (Two Phase Operation) • K-DEMO has two operation phases, Phase I and Phase II. Though the operation phase I K-DEMO does not need to demonstrate the competitiveness in COE(Cost of Electricity), the operation phase II K-DEMO need to demonstrate the competitiveness in COE. • All power core and plant subsystems in K-DEMO plant must be representative of those in the commercial plant. Extrapolation of technologies from K-DEMO to a commercial reactor should be straight forward. Practically all technologies to be used in commercial reactors should be demonstrated in the K-DEMO. Also, extrapolation of performance parameters between K-DEMO and commercial reactors should be minimized. • K-DEMO shall be operated and maintained with remote handling equipment. This is an absolute prerequisite as the neutron level during operation and radioactive activation during maintenance periods will be excessive for human intervention inside the power core building and hot cell bio-shields at all times • The operation phase II K-DEMO plant need to achieve an overall all plant availability larger than 70%. • The operation phase I K-DEMO is not considered as the final DEMO. It is a kind of test facility for a commercial reactor. But the operation phase II K-DEMO will require a major up-grade by replacing the blanket & divertorsystem and others if required. • Construction cost for K-DEMO should be minimized and the size of the K-DEMO Tokamak is expected to be smaller or similar size of ITER Tokamak. • The operation phase I K-DEMO • At initial stage, many of ports will be used for diagnostics for the operation and burning plasma physics study, but many of them will be transformed to the CTF (Component Test Facility). • At least more than one port will be designated for the CTF including blanket test facility. • It should demonstrate the net electricity generation (Qeng > 1) and the self-sufficient Tritium cycle (TBR > 1.05). • The operation phase II K-DEMO • Though there will be a major upgrade of In-Vessel-Components, at least one port will be designated for CTF for future studies. • It is expected to demonstrate the net electricity generation larger than 450 MWeand the self-sufficient Tritium cycle .

  13. Optimization Concept of K-DEMO • Demonstrate a reasonable net-electricity (> 300 MW) generation with a minimum cost • Provide a maximum flexibility ARIES-AT CREST ARIES-RS K-DEMO (Stage II) PPCS-D SSTR ITER K-DEMO (Stage I)

  14. K-DEMODesign Parameters

  15. DEMO TF CICC Parameter(Helical Spiral) • Cable Pattern: (3SC)x4x6x6x(5+Spiral)[2160 SC strand] • Void Fraction : 28.85% • Strand : • High Jc (> 2600A/mm2) Nb3Sn Strand • Cu/Non-Cu = 1.0 • HelicalSpiral : ID = 8 mm OD = 12 mm • Insulation : 1.6 mm (with Voltage Tap) • 0.1 mm Kapton 400% • 0.3 mm S-glass 400% • Jacket Thickness : 5.0 mm • Twist Pitch • 1st Stage 45 ± 5 mm • 2nd Stage 85 ± 10 mm • 3rd Stage 125 ± 15 mm • 4th Stage 245 ± 20 mm • 5th Stage 435 ± 20 mm • Wrapping Tape Thickness • Sub-cable : 0.08 m 40% • Sub-cablewrap width : 15 mm • Cable : 0.08 mm 140% • Final wrap width : 40 mm • SC Strand Weight : ~600 ton R 3 1.6 5.0 60.8 70.8 Insulation 74.0 Jacket 30.8 40.8 44.0 DEMO TF CICC Cross-section

  16. DEMO Small TF CICC Parameter • Cable Pattern: (3SC)x4x5x(6+Central Spiral)[360SC strand] • Void Fraction : 31.03% • Strand : • High Jc (> 2600A/mm2) Nb3Sn Strand • Cu/Non-Cu = 1.0 • CentralSpiral : ID = 7 mm OD = 10 mm • Insulation : 1.6 mm (with Voltage Tap) • 0.1 mm Kapton 400% • 0.3 mm S-glass 400% • Jacket Thickness : 5.0 mm • Twist Pitch • 1st Stage 45 ± 5 mm • 2nd Stage 85 ± 10 mm • 3rd Stage 125 ± 15 mm • 4th Stage 335 ± 20 mm • Wrapping Tape Thickness • Sub-cable : 0.08 m 40% • Sub-cablewrap width : 15 mm • Cable : 0.08 mm 200% • Final wrap width : 40 mm 1.6 5.0 R 3 Insulation 20.8 30.8 34.0 Jacket 20.8 30.8 34.0 DEMO TF CICC Cross-section

  17. Inboard Cross-Section of TF Coil (Option I) • R = 6.0 m, a = 1.8 m • Small CICC Coil : 16 x 8turns Large CICC Coil : 12 x 5turns (Total : 188 turns) • Magnetic Field at Plasma Center : ~7.72 Tesla (Bpeak~ 16 Tesla, T-margin > 1 K) • Nominal Current : 77.0 kA • Conductor Length : • LQP = ~777 m (Quadruple Pancake) Total : ~445 tons • SDP = ~634 m (Double Pancake) Total : ~163 tons Clearance Filled with Glass Fiber (5 mm) Ground Wrap (5 mm) 2050 mm 2388 mm 2660 mm 2890 mm 2970 mm

  18. Outboard Cross-Section of TF Coil (Option I) 870mm Clearance Filled with Glass Fiber (5 mm) 106 mm Space (Filled with 316) for Turn Transition and Feed Through (90 mm) 278 mm Ground Wrap (5 mm) 550mm 10910 mm 10990 mm 198 mm 11210 mm 112310 mm 11582 mm 11780 mm

  19. Inboard Cross-Section of TF Coil (Option II) • R = 6.5 m, a = 2.0 m • Small CICC Coil : 18 x 8turns Large CICC Coil : 12 x 5 turns (Total : 204 turns) • Magnetic Field at Plasma Center : ~7.72 Tesla (Bpeak ~ 16 Tesla, T-margin > 1K) • Nominal Current : 76.9kA • Conductor Length : • LQP = ~825 m (Quadruple Pancake) (Total : ~480 ton) • SDP = ~680 m (Double Pancake) (Total : ~200 ton) Clearance Filled with Glass Fiber (5 mm) Ground Wrap (5 mm) 2150 mm 2633 mm 2905 mm 3135 mm 3220 mm

  20. Outboard Cross-Section of TF Coil (Option II) 880 mm Clearance Filled with Glass Fiber (5 mm) Space (Filled with 316) for Turn Transition and Feed Through (90 mm) 106 mm 244 mm Ground Wrap (5 mm) 550mm 11810 mm 203 mm 11895 mm 12115 mm 12215 mm 12487 mm 12690 mm

  21. DEMO TF CICC Parameter(Option II-A) • Cable Pattern: (3SC)x4x5x6x(5 + Helical Spiral) [1800 SC strand] • Void Fraction : 28.1% • Strand : • High Jc (> 2600A/mm2) Nb3Sn Strand • Cu/Non-Cu = 1.0 • HelicalSpiral : ID = 8 mm OD = 12 mm • Insulation : 1.6 mm (including Voltage Tap) • 0.1 mm Kapton 400% • 0.3 mm S-glass 400% • Jacket Thickness : 5.0 mm • Twist Pitch • 1st Stage 45 ± 5 mm • 2nd Stage 85 ± 10 mm • 3rd Stage 125 ± 15 mm • 4th Stage 245 ± 20 mm • 5th Stage 435 ± 20 mm • Wrapping Tape Thickness • Sub-cable : 0.08 m 40% • Sub-cable wrap width : 15 mm • Cable : 0.08 mm 140% • Final wrap width : 40 mm R 3 1.6 5.0 Insulation 58.8 68.8 72.0 Jacket 26.8 36.8 40.0 DEMO TF CICC Cross-section

  22. Inboard Cross-Section of TF Coil (Option II-A) • Selected for Detailed Study • R = 6.8 m, a = 2.1 m • Small CICC Coil : 20 x 9 turns Large CICC Coil : 12 x 5 turns (Total : 240 turns) • Magnetic Field at Plasma Center : ~7.4 Tesla (Bpeak ~ 16 Tesla, T-margin > 1 K) • Nominal Current : 65.52 kA • Conductor Length : • LQP = ~872 m (Quadruple Pancake) (Total : ~418 ton) • SDP = ~810 m (Double Pancake) (Total : ~258 ton) Clearance Filled with Glass Fiber (5 mm) Ground Wrap (5 mm) 2150 mm 2619 mm 2925 mm 3135 mm 3220 mm

  23. Outboard Cross-Section of TF Coil (Option II-A) 925 mm Clearance Filled with Glass Fiber (5 mm) Space (Filled with 316) for Turn Transition and Feed Through (120 mm) 118 mm 210 mm Ground Wrap (5 mm) 550mm 12210 mm 204 mm 12295 mm 12525 mm 12655 mm 12961 mm 13165 mm

  24. Inboard Cross-Section of TF Coil (Option III) • R = 7.15 m, a = 2.2 m • Small CICC Coil : 18 x 8 turns, Large CICC Coil : 12 x 6 turns (Total : 216 turns) • Magnetic Field at Plasma Center : ~7.5 Tesla (Bpeak ~ 16 Tesla, T-margin > 1 K) • Nominal Current : 77.6 kA • Conductor Length : • LQP = ~ 1102 m (Quadruple Pancake) (~643 ton) • SDP = ~ 763 m (Double Pancake) (~218 ton) Clearance Filled with Glass Fiber (5 mm) Ground Wrap (5 mm) 2849 mm 2385 mm 3121 mm 3395 mm 3480 mm

  25. Outboard Cross-Section of TF Coil (Option III) 955 mm Clearance Filled with Glass Fiber (5 mm) Space (Filled with 316) for Turn Transition and Feed Through (120 mm) 106 mm 244 mm Ground Wrap (5 mm) 550 mm 13025 mm 204 mm 13110 mm 13374 mm 13776 mm 13504 mm 13980 mm

  26. Joint Scheme of Inner Magnet From PS (or Inner Magnet Lead) Helium Feed Through Inter Coil Joint Inter Coil Joint Layer Transition Layer Transition Layer Transition To Neighboring Inner Magnet Lead

  27. Joint Scheme of Outer Magnet From Outer (or Last Inner) Magnet Lead To Neighboring Outer Magnet Lead

  28. 3D Modeling of TF Magnet

  29. 3D Modeling of TF Assembly

  30. TF Coil Structure

  31. DEMO CS CICC Parameter (Corner Channel) • Cable Pattern: (3SC)x3x4x4x6 [864 SC strand] • Void Fraction : 37.19% • Strand : • ITER Type (Jc ~ 1050A/mm2) Nb3Sn Strand • Cu/Non-Cu = 1.2 • NO COOLING SPIRAL  Corner Channel • Jacket Thickness : 5 mm • Insulation : 2.0 mm (with Voltage Tap) • 0.1 mm Kapton 400% • 0.4 mm S-glass 400% • Twist Pitch • 1st Stage 45 ± 5 mm • 2ndStage 85 ± 10 mm • 3rdStage 145 ± 10 mm • 4thStage 250 ± 15 mm • 5thStage 420 ± 20 mm • Wrapping Tape Thickness • Sub-cable : 0.08 mm 40% • Sub-cable wrap width : 15 mm • Cable : 0.5 mm 60% • Final wrap width : 7 mm R 3 2 5 Insulation 54 50 40 Jacket 34 30 20 DEMO CS CICC Cross-section

  32. Cross-Section of CS Coils (Option I) • Number of Turns : 14 (Total SC strand weight : ~120 tons) • Number of Layers : CS1 & CS2 : 30 layers, CS3 : 24 layers • Magnetic Field at Center : ~12.52 Tesla (Bpeak < 12.774 Tesla) • Conductor Unit Length : 895 m (CS1 & CS2 : UL x 5, CS3 : UL x 4) • Gap Between Coils : 50 mm 1296 mm 1620 mm 1420 mm 1896 mm 1420 mm 1896 mm CS3 Coils CS1 & CS2 Coil

  33. Magnetic Field of CS Coils (Option I) • Magnetic Field • Field at Center : ~12.835 Tesla • Peak Field : ~ 13.086 Tesla • Maximum Flux Swing : ~81 V·sec • Nominal Current : 44 kA (Current can be increased) • Temperature Margin ~ 1.4 K

  34. Cross-Section of CS Coils (Option II) • Number of Turns : 14 (Total SC strand weight : ~145 tons) • Number of Layers : CS1, CS2 & CS2 : 30 layers • Magnetic Field at Center : ~13.12 Tesla (Bpeak < 13.37 Tesla) • Conductor Unit Length : 950 m (CS1, CS2 & CS3 : UL x 5) • Gap Between Coils : 50 mm 1620 mm 1500 mm 1976 mm CS3 Coils CS1 & CS2 & CS3 Coil

  35. Magnetic Field of CS Coils (Option II) • Magnetic Field • Field at Center : ~13.12 Tesla • Peak Field : ~ 13.37 Tesla • Maximum Flux Swing : ~93 V·sec • Nominal Current : 45 kA (Current can be increased) • Temperature Margin ~ 1.1 K

  36. Cross-Section of CS Coils (Option III) • Number of Turns : 14 (Total SC strand weight : ~165 tons) • Number of Layers : CS1, CS2 & CS2 : 30 layers • Magnetic Field at Center : ~13.1 Tesla (Bpeak < 13.35 Tesla) • Conductor Unit Length : 1070 m (CS1, CS2 & CS3 : UL x 5) • Gap Between Coils : 50 mm 1620 mm 1730 mm 2206 mm CS3 Coils CS1 & CS2 & CS3 Coil

  37. Magnetic Field of CS Coils (Option III) • Magnetic Field • Field at Center : ~13.12 Tesla • Peak Field : ~ 13.41 Tesla • Maximum Flux Swing : ~123 V·sec • Nominal Current : 46 kA (Current can be increased) • Temperature Margin ~ 1.1 K

  38. Test Samples of Conductors DEMO CS CICC(corner channel)& Large TF CICC (helical spiral) Thanks to Antonio della Corte & his colleagues (ENEA/ICAS) !!

  39. Concept of Vertical Maintenance (Pilot Plant) • Vertical maintenance of all in-vessel components for Pilot Plant (PPPL) Case Internal VV maintenance space expanded Enlarged TF Horizontal assisted maintenance VV (~150° C) Semi-permanent Inboard Shield structure (~350° C) Horizontal assisted maintenance DCLL PbLi/He Base Blanket (350/450° C) Gravity support / coolant supply plenum Coolant supply from below

  40. 3D Modeling of Blanket System

  41. 3D Modeling of Blanket System

  42. 3D Modeling of Blanket System

  43. 3D Modeling of Blanket System

  44. 3D Modeling of Blanket System

  45. 3D Modeling of Blanket System

  46. 3D Modeling of Blanket System

  47. Assumption for the Thickness of Blanket Inboard-Side Blanket [Thickness = 1000 mm] Blanket FW 150 85 38 50 200 70 240 167 Manifold& Structures Be Be Shield Li4SiO4 Structural Material Cooling channel W Be B4C Outboard-Side Blanket [Thickness = 1225 mm] FW Blanket 200 280 150 100 85 40 20 50 200 100 Manifold& Structures Be Be Shield

  48. Radial Build of K-DEMO [unit : mm] (Option I) Plasma CS TF VV Blan- ket Blanket VV TF 1420 SOL SOL TS TS 1896 Space for Vertical Maintenance 2050 3000 3170 3300 4100 4200 6000 7800 7900 9100 10100 10480 10910 11780

  49. Radial Build of K-DEMO [unit : mm] (Option II) Plasma CS TF VV Blan- ket Blanket VV TF 1500 TS SOL SOL TS 1976 Space for Vertical Maintenance 2150 3220 3420 3550 4550 4650 6650 8650 8750 9975 11175 11555 11985 12895

  50. Radial Build of K-DEMO [unit : mm] (Option II-A) Plasma CS TF VV Blan- ket Blanket VV TF 1500 TS SOL SOL TS 1976 Space for Vertical Maintenance 2150 3220 3420 3550 4600 4700 6800 8900 9000 10200 11400 11780 12210 13135

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