Implementation of a long leg X-point target divertor in the ARC fusion pilot plant
|
|
- Cuthbert Stevenson
- 5 years ago
- Views:
Transcription
1 Implementation of a long leg X-point target divertor in the ARC fusion pilot plant A.Q. Kuang, N.M. Cao, A.J. Creely, C.A. Dennett, J. Hecla, H. Hoffman, M. Major, J. Ruiz Ruiz, R.A. Tinguely, E.A. Tolman D. Brunner, B. LaBombard, B.N. Sorbom, D.G. Whyte Massachusetts Institute of Technology, Cambridge, MA P. Grover, C. Laughman Mitsubishi Electric Research Laboratories, Cambridge, MA See Dennett JP Tuesday, 2 pm
2 ARC A compact high-field tokamak ITER power levels (P fusion = 525 MW) in a JET sized (R 0 = 3.3 m) tokamak. Key Design Parmeter Value Fusion Power 525 MW Major Radius 3.3 m Toroidal Magnetic Field 9.2 T Sorbom. B.N., et al. (2015). Fusion Engineering and Design. Vol. 100, p Plant Lifetime 9 years 1 of 12
3 ARC A compact high-field tokamak ITER power levels (P fusion = 525 MW) in a JET sized (R 0 = 3.3 m) tokamak. High Temperature Superconductors (HTS) enable on-axis field of 9.2 Tesla. Key Design Parmeter Value Fusion Power 525 MW Major Radius 3.3 m Toroidal Magnetic Field 9.2 T Sorbom. B.N., et al. (2015). Fusion Engineering and Design. Vol. 100, p Plant Lifetime 9 years 1 of 12
4 ARC A compact high-field tokamak ITER power levels (P fusion = 525 MW) in a JET sized (R 0 = 3.3 m) tokamak. High Temperature Superconductors (HTS) enable on-axis field of 9.2 Tesla. Toroidal field magnets designed with demountable joints. Key Design Parmeter Value Fusion Power 525 MW Major Radius 3.3 m Toroidal Magnetic Field 9.2 T Sorbom. B.N., et al. (2015). Fusion Engineering and Design. Vol. 100, p Plant Lifetime 9 years 1 of 12
5 ARC A compact high-field tokamak ITER power levels (P fusion = 525 MW) in a JET sized (R 0 = 3.3 m) tokamak. High Temperature Superconductors (HTS) enable on-axis field of 9.2 Tesla. Toroidal field magnets designed with demountable joints. Vacuum vessel immersed in a molten FLiBe blanket that acts as both the neutron shield and the coolant. Key Design Parmeter Value Fusion Power 525 MW Major Radius 3.3 m Toroidal Magnetic Field 9.2 T Sorbom. B.N., et al. (2015). Fusion Engineering and Design. Vol. 100, p Plant Lifetime 9 years 1 of 12
6 ARC A compact high-field tokamak ITER power levels (P fusion = 525 MW) in a JET sized (R 0 = 3.3 m) tokamak. High Temperature Superconductors (HTS) enable on-axis field of 9.2 Tesla. Toroidal field magnets designed with demountable joints. Vacuum vessel immersed in a molten FLiBe blanket that acts as both the neutron shield and the coolant. Vacuum vessel designed to be replaced every 1-2 years during the 9 full power years of the plant lifetime. Key Design Parmeter Fusion Power Major Radius Toroidal Magnetic Field Value 525 MW 3.3 m 9.2 T Sorbom. B.N., et al. (2015). Fusion Engineering and Design. Vol. 100, p Plant Lifetime 9 years 1 of 12
7 ARC A compact high-field tokamak ITER power levels (P fusion = 525 MW) in a JET sized (R 0 = 3.3 m) tokamak. High Temperature Superconductors (HTS) enable on-axis field of 9.2 Tesla. Toroidal field magnets designed with demountable joints. Vacuum vessel immersed in a molten FLiBe blanket that acts as both the neutron simplified shield and divertor the coolant. geometry. Vacuum vessel designed to be replaced every 1-2 years during the 9 full power years of the plant lifetime. However, the initial design for ARC had an intentionally Key Design Parmeter Fusion Power Major Radius Toroidal Magnetic Field Value 525 MW 3.3 m 9.2 T Sorbom, B.N., et al. (2015). Fusion Engineering and Design. Vol. 100, p Plant Lifetime 9 years 1 of 12
8 Outline Demountable TF coils and the FLiBe immersion blanket enable: MCNP simulations were performed for the full 3D vacuum vessel geometry Internal PF coils Implementation of advanced divertor geometries Maintaining core plasma volume Shielded PF coils Keeping tritium breeding ratio greater than unity 2 of 12
9 Outline Demountable TF coils and the FLiBe immersion blanket enable: MCNP simulations were performed for the full 3D vacuum vessel geometry Internal PF coils Implementation of advanced divertor geometries Maintaining core plasma volume Shielded PF coils Keeping tritium breeding ratio greater than unity Double-null magnetic topology with secondary X-point target divertor configuration was selected for maximum power handling capabilities. 2 of 12
10 Outline Demountable TF coils and the FLiBe immersion blanket enable: MCNP simulations were performed for the full 3D vacuum vessel geometry Internal PF coils Implementation of advanced divertor geometries Maintaining core plasma volume Shielded PF coils Keeping tritium breeding ratio greater than unity Double-null magnetic topology with secondary X-point target divertor configuration was selected for maximum power handling capabilities. Long leg passively stable robust divertor systems provides a means to handle and actively control the high heat exhaust in a fusion reactor. 2 of 12
11 Original ARC magnetic topology with simplified divertor 3 of 12
12 Original ARC magnetic topology with simplified divertor Original ARC divertor geometry was intentionally over simplified. 3 of 12
13 Need to select a magnetic topology that can cope with reactor relevant divertor heat fluxes Fusion power plants all face the same problem of having extreme heat flux levels to the divertor LH LH ARC ACT2 C-Mod 8T ADX 8T 1 LaBombard, B., et al. (2015) Nuclear Fusion. Vol. 55, No. 5. B [T] 6 4 KSTAR EAST SST-1 DIII-D LH LH ACT1 ITER C-Mod * 5.4T JET AUG ADX 6.5T Maximum possible Psol B/R from device Psol B/R at L-H power threshold JT-60SA 2 TCV Original ITER Q DT =10 NSTX-U operation point world tokamaks * MAST q // ~ Psol B/R [MW-T/m] q [GW/m 2 ] LH 4 of 12
14 Need to select a magnetic topology that can cope with reactor relevant divertor heat fluxes Fusion power plants all face the same problem of having extreme heat flux levels to the divertor LH LH ARC ACT2 C-Mod 8T ADX 8T 1 LaBombard, B., et al. (2015) Nuclear Fusion. Vol. 55, No. 5. B [T] 6 4 KSTAR EAST SST-1 DIII-D LH LH ACT1 ITER C-Mod * 5.4T JET AUG ADX 6.5T Maximum possible Psol B/R from device Psol B/R at L-H power threshold JT-60SA 2 TCV Original ITER Q DT =10 NSTX-U operation point world tokamaks * MAST q // ~ Psol B/R [MW-T/m] q [GW/m 2 ] LH 4 of 12
15 Need to select a magnetic topology that can cope with reactor relevant divertor heat fluxes Fusion power plants all face the same problem of having extreme heat flux levels to the divertor 1. Data from Alcator C-Mod, H-Mode, 0.8 MA λ q ~ 1 mm Double null geometry allows for the power sharing between outer strike points and reduces heat flux to the inner strike point. 1 1 LaBombard, B., et al. (2015) Nuclear Fusion. Vol. 55, No Brunner, D., et al. (in progress) Nuclear Fusion. Brunner, D. et al. (2016) APS DPP, San Jose. 4 of 12
16 Need to select a magnetic topology that can cope with reactor relevant divertor heat fluxes Fusion power plants all face the same problem of having extreme heat flux levels to the divertor 1. Double null geometry allows for the power sharing between outer strike points and reduces heat flux to the inner strike point. 2 X-point target divertor geometry has been shown in simulation to have the highest detachment threshold and largest stable detachment power window 3. 1 LaBombard, B., et al. (2015) Nuclear Fusion. Vol. 55, No Brunner, D., et al. (in progress) Nuclear Fusion. Brunner, D. et al. (2016) APS DPP, San Jose. 3 Umansky, M., et al. (2017), Physics of Plasmas. Vol of 12
17 A long legged X-point divertor magnetic geometry Significant proportion of the magnetic volume is not being utilized due to the need for neutron shielding. 5 of 12
18 A long legged X-point divertor magnetic geometry Significant proportion of the magnetic volume is not being utilized due to the need for neutron shielding. Double-null magnetic topology with secondary X-point target divertor 1 May allow for stable, detached operation 2. 1 LaBombard, B., et al. (2015), Nuclear Fusion. Vol. 55, No Umansky, M., et al. (2017), Physics of Plasmas. Vol of 12
19 A long legged X-point divertor magnetic geometry Significant proportion of the magnetic volume is not being utilized due to the need for neutron shielding. Double-null magnetic topology with secondary X-point target divertor 1 May allow for stable, detached operation 2. Internal PF coils made possible by demountable TF coil design 3. 1 LaBombard, B., et al. (2015), Nuclear Fusion. Vol. 55, No Umansky, M., et al. (2017), Physics of Plasmas. Vol Mangiarotti, F.J., et al. (2015), IEEE Transactions on Applied Superconductivity. Vol. 25, Issue 3. 5 of 12
20 Reduced coil current-turns and size Simple coil set involving 3 divertor coils. 6 of 12
21 Reduced coil current-turns and size Simple coil set involving 3 divertor coils. Reduced PF coil current-turns due to proximity to the plasma (25% of currentturns in ITER PF). 6 of 12
22 Reduced coil current-turns and size Simple coil set involving 3 divertor coils. Reduced PF coil current-turns due to proximity to the plasma (25% of currentturns in ITER PF). Coils sized to critical current densities of 350 A/mm 2 (performance based of 2015 REBCO HTS data operated at 20 K and a background magnetic field of 17 T). HTS cable has yet to be developed, but preliminary design work suggests that 20% superconductors and 80% structure to be a conservative estimate. PF coils shown in figure are to scale. 6 of 12
23 Reduced coil current-turns and size Simple coil set involving 3 pull coils. Reduced PF coil current-turns due to proximity to the plasma (25% of currentturns in ITER PF). Coils sized to critical current densities of 350 A/mm 2 (performance based of 2015 REBCO HTS data operated at 20 K and a background magnetic field of 17 T). HTS cable has yet to be developed, but preliminary design work suggests that 20% superconductors and 80% structure to be a conservative estimate. PF coils shown in figure are to scale. All while maintaining: TF coil geometry Tritium breeding ratio (TBR) TF and PF coil lifetimes 6 of 12
24 PF and TF coil lifetimes greater than 9 FPY ARC has a plant lifetime of 9 full power years (FPY) set by neutrons at the inner leg of the TF remains unchanged. Energetic Neutron flux (>100keV) 1.6E15 9.2E12 5.3E10 3.1E8 1.8E6 n/cm^2*s 7 of 12
25 PF and TF coil lifetimes greater than 9 FPY ARC has a plant lifetime of 9 full power years (FPY) set by neutrons at the inner leg of the TF remains unchanged. The PF coils achieved similar coil lifetime requirements with the addition of a solid neutron shield layer at the edge of the FLiBe tank FPY 11.3 FPY Energetic Neutron flux (>100keV) 1.6E15 9.2E12 5.3E10 3.1E8 1.8E6 n/cm^2*s 7 of 12
26 PF and TF coil lifetimes greater than 9 FPY ARC has a plant lifetime of 9 full power years (FPY) set by neutrons at the inner leg of the TF remains unchanged. The PF coils achieved similar coil lifetime requirements with the addition of a solid neutron shield layer at the edge of the FLiBe tank. Lifetime estimate based on data established for NB 3 Sn ( n/cm 2, for neutron energies > 100 kev). This is conservative as HTS is expected to have higher thresholds FPY 11.3 FPY Energetic Neutron flux (>100keV) 1.6E15 9.2E12 5.3E10 3.1E8 1.8E6 n/cm^2*s 1 Bromberg, L., et al. (2001). Fusion Engineering and Design, Vol. 54, p167 7 of 12
27 Tritium breeding ratio maintained greater than unity 5 No loss of TBR due to the large volume of breeding material that is now taken up by the divertor. D-T Plasma First wall FLiBe in coolant channels External FLiBe tank Tritium produced per source neutron of 12
28 Tritium breeding ratio maintained greater than unity 5 No loss of TBR due to the large volume of breeding material that is now taken up by the divertor. With FLiBe flowing in the cooling channels of the vacuum vessel where fast neutron dominate the spectrum. D-T Plasma First wall FLiBe in coolant channels External FLiBe tank Tritium produced per source neutron of 12
29 Tritium breeding ratio maintained greater than unity 5 No loss of TBR due to the large volume of breeding material that is now taken up by the divertor. With FLiBe flowing in the cooling channels of the vacuum vessel where fast neutron dominate the spectrum. It is optimally located for tritium generation. Thus maintaining a TBR of D-T Plasma First wall FLiBe in coolant channels External FLiBe tank Tritium produced per source neutron of 12
30 Reduced neutron damage in divertor due to leg geometry Neutron damage in the divertor region is significantly reduced due to extended leg. Divertor Region dpa/yr He/dpa ~ Midplane dpa/yr He/dpa ~ of 12
31 Reduced neutron damage in divertor due to leg geometry Neutron damage in the divertor region is significantly reduced due to extended leg. Softening of the neutron spectrum for divertor components of the vacuum vessel further reduce He production. ~10 2 reduction in the magnitude of the neutron spectrum Reduced fast neutron population Divertor Region dpa/yr He/dpa ~ Midplane dpa/yr He/dpa ~ of 12
32 The ARC divertor seperates and resolves key challenges Plasma erosion and high heat flux Stable detachment across a wide power window 1 reduces plasma temperature at plasma facing components and minimizes sputtering without affecting core plasma performance. Long leg geometry spreads heat flux over a larger area. Initial simulations 2 have peak heat fluxes of ~6 MW/m 2. Harsh neutron environment Reduced neutron damage levels implies a possible separation of function between high heat flux handling and neutron damage resistant components. Components only have to last 1-2 year before vacuum vessel is replaced of 12
33 The ARC divertor seperates and resolves key challenges Plasma erosion and high heat flux Stable detachment across a wide power window 1 reduces plasma temperature at plasma facing components and minimizes sputtering without affecting core plasma performance. Long leg geometry spreads heat flux over a larger area. Initial simulations 2 have peak heat fluxes of ~6 MW/m 2. Harsh neutron environment Reduced neutron damage levels implies a possible separation of function between high heat flux handling and neutron damage resistant components. Components only have to last 1-2 year before vacuum vessel is replaced 3. P sol = 88 MW 0.5% Neon Super-X case λ q ~0.6 mm 1 Umansky, M., et al. (2017), Physics of Plasmas. Vol Wigram, M., et al. (2017), Plasma Edge Theory Conference, Marseilli, France. 10 of 12
34 The ARC divertor seperates and resolves key challenges Plasma erosion and high heat flux Stable detachment across a wide power window 1 reduces plasma temperature at plasma facing components and minimizes sputtering without affecting core plasma performance. Long leg geometry spreads heat flux over a larger area. Initial simulations 2 have peak heat fluxes of ~6 MW/m 2. Harsh neutron environment Reduced neutron damage levels implies a possible separation of function between high heat flux handling and neutron damage resistant components. Components only have to last 1-2 year before vacuum vessel is replaced 3. P sol = 88 MW 0.5% Neon Super-X case λ q ~0.6 mm 1 Umansky, M., et al. (2017), Physics of Plasmas. Vol Wigram, M., et al. (2017), Plasma Edge Theory Conference, Marseilli, France. 3 Sorbom, B.N., et al. (2015). Fusion Engineering and Design. Vol. 100, p of 12
35 Long leg divertors provide a means to handle and actively control high divertor heat exhaust Present experiments use active feedback systems to control divertor detachment due to the narrow power window. But this cannot scale to a reactor 1 : Changes in heat flux can occur on < 10 ms time scales while feedback systems respond at ~1 s timescales. Sensors used today likely would not survive in a reactor. 1 Brunner, D., et al. (2017) Nuclear Fusion. Vol. 57, No.8. 2 Umansky, M., et al. (2017), Physics of Plasmas. Vol of 12
36 Long leg divertors provide a means to handle and actively control high divertor heat exhaust Present experiments use active feedback systems to control divertor detachment due to the narrow power window. But this cannot scale to a reactor 1 : Changes in heat flux can occur on < 10 ms time scales while feedback systems respond at ~1 s timescales. Sensors used today likely would not survive in a reactor. X-point Target Ionization front location P in Increasing power to the divertor A robust passively stable detached divertor is the key. P in P in 1 Brunner, D., et al. (2017) Nuclear Fusion. Vol. 57, No.8. 2 Umansky, M., et al. (2017), Physics of Plasmas. Vol of 12
37 Long leg divertors provide a means to handle and actively control high divertor heat exhaust Present experiments use active feedback systems to control divertor detachment due to the narrow power window. But this cannot scale to a reactor 1 : Changes in heat flux can occur on < 10 ms time scales while feedback systems respond at ~1 s timescales. Sensors used today likely would not survive in a reactor. X-point Target Ionization front location P in Increasing power to the divertor A robust passively stable detached divertor is the key. Focus on adjusting detachment front location over manageable timescales (~1 sec). Reliant only on neutron-tolerant diagnostics such as microwave reflectometry/interferometry system. P in P in 1 Brunner, D., et al. (2017) Nuclear Fusion. Vol. 57, No.8. 2 Umansky, M., et al. (2017), Physics of Plasmas. Vol of 12
38 Conclusion Demountable TF coils and the FLiBe immersion blanket enable: MCNP simulations were performed for the full 3D vacuum vessel geometry Internal PF coils Implementation of advanced divertor geometries Maintaining core plasma volume Shielded PF coils Keeping tritium breeding ratio greater than unity Double-null magnetic topology with secondary X-point target divertor configuration was selected for maximum power handling capabilities. Long leg passively stable robust divertor systems provides a means to handle and actively control the high heat exhaust in a fusion reactor. See Dennett JP Tuesday, 2 pm 12 of 12
Conceptual design study for heat exhaust management in the ARC fusion pilot plant
Conceptual design study for heat exhaust management in the ARC fusion pilot plant A.Q. Kuang 1, N.M. Cao 1, A.J. Creely 1, C.A. Dennett 2, J. Hecla 2, B. LaBombard 1, R.A. Tinguely 1, E.A. Tolman 1, H.
More informationStudies of Next-Step Spherical Tokamaks Using High-Temperature Superconductors Jonathan Menard (PPPL)
Studies of Next-Step Spherical Tokamaks Using High-Temperature Superconductors Jonathan Menard (PPPL) 22 nd Topical Meeting on the Technology of Fusion Energy (TOFE) Philadelphia, PA August 22-25, 2016
More informationSMALLER & SOONER: EXPLOITING NEW TECHNOLOGIES FOR FUSION S DEVELOPMENT
MIT Plasma Science & Fusion Center SMALLER & SOONER: EXPLOITING NEW TECHNOLOGIES FOR FUSION S DEVELOPMENT Dennis Whyte MIT Plasma Science and Fusion Center MIT Nuclear Science and Engineering With grateful
More informationDemountable Superconducting Magnet Coils
FESAC TEC Report 1 Demountable Superconducting Magnet Coils A strategic technology to address key nuclear materials, construction, and maintenance issues Brandon Sorbom, Bob Mumgaard, Joseph Minervini,
More informationSmaller & Sooner: How a new generation of superconductors can accelerate fusion s development
Smaller & Sooner: How a new generation of superconductors can accelerate fusion s development Dennis Whyte MIT Nuclear Science & Engineering Plasma Science Fusion Center June 2012 American Security Project
More informationMission Elements of the FNSP and FNSF
Mission Elements of the FNSP and FNSF by R.D. Stambaugh PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION Presented at FNST Workshop August 3, 2010 In Addition to What Will Be Learned
More informationOV/2-5: Overview of Alcator C-Mod Results
OV/2-5: Overview of Alcator C-Mod Results Research in Support of ITER and Steps Beyond* E.S. Marmar on behalf of the C-Mod Team 25 th IAEA Fusion Energy Conference, Saint Petersburg, Russia, 13 October,
More informationCritical Gaps between Tokamak Physics and Nuclear Science. Clement P.C. Wong General Atomics
Critical Gaps between Tokamak Physics and Nuclear Science (Step 1: Identifying critical gaps) (Step 2: Options to fill the critical gaps initiated) (Step 3: Success not yet) Clement P.C. Wong General Atomics
More informationDEMO Concept Development and Assessment of Relevant Technologies. Physics and Engineering Studies of the Advanced Divertor for a Fusion Reactor
FIP/3-4Rb FIP/3-4Ra DEMO Concept Development and Assessment of Relevant Technologies Y. Sakamoto, K. Tobita, Y. Someya, H. Utoh, N. Asakura, K. Hoshino, M. Nakamura, S. Tokunaga and the DEMO Design Team
More informationFusion Development Facility (FDF) Mission and Concept
Fusion Development Facility (FDF) Mission and Concept Presented by R.D. Stambaugh PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION University of California Los Angeles FNST Workshop
More informationPossibilities for Long Pulse Ignited Tokamak Experiments Using Resistive Magnets
PFC/JA-91-5 Possibilities for Long Pulse Ignited Tokamak Experiments Using Resistive Magnets E. A. Chaniotakis L. Bromberg D. R. Cohn April 25, 1991 Plasma Fusion Center Massachusetts Institute of Technology
More informationInnovative fabrication method of superconducting magnets using high T c superconductors with joints
Innovative fabrication method of superconducting magnets using high T c superconductors with joints (for huge and/or complicated coils) Nagato YANAGI LHD & FFHR Group National Institute for Fusion Science,
More informationCore Design. Derek Sutherland, Cale Kasten Choongki Sung, Tim Palmer Paul Bonoli, Dennis Whyte
Core Design Derek Sutherland, Cale Kasten Choongki Sung, Tim Palmer Paul Bonoli, Dennis Whyte 22.63 - May 17, 2012 Primary Design Goals Qp ~ 25 and Qe > 3, with thermal output of ~ 500 MW. Develop a robust,
More informationA SUPERCONDUCTING TOKAMAK FUSION TRANSMUTATION OF WASTE REACTOR
A SUPERCONDUCTING TOKAMAK FUSION TRANSMUTATION OF WASTE REACTOR A.N. Mauer, W.M. Stacey, J. Mandrekas and E.A. Hoffman Fusion Research Center Georgia Institute of Technology Atlanta, GA 30332 1. INTRODUCTION
More informationDeveloping a Robust Compact Tokamak Reactor by Exploiting New Superconducting Technologies and the Synergistic Effects of High Field D.
Developing a Robust Compact Tokamak Reactor by Exploiting ew Superconducting Technologies and the Synergistic Effects of High Field D. Whyte, MIT Steady-state tokamak fusion reactors would be substantially
More informationPhysics of fusion power. Lecture 14: Anomalous transport / ITER
Physics of fusion power Lecture 14: Anomalous transport / ITER Thursday.. Guest lecturer and international celebrity Dr. D. Gericke will give an overview of inertial confinement fusion.. Instabilities
More informationNuclear Fusion and ITER
Nuclear Fusion and ITER C. Alejaldre ITER Deputy Director-General Cursos de Verano UPM Julio 2, 2007 1 ITER the way to fusion power ITER ( the way in Latin) is the essential next step in the development
More informationPhysics and Engineering Studies of the Advanced Divertor for a Fusion Reactor
1 FIP/3-4Ra Physics and Engineering Studies of the Advanced Divertor for a Fusion Reactor N. Asakura 1, K. Hoshino 1, H. Utoh 1, K. Shinya 2, K. Shimizu 3, S. Tokunaga 1, Y.Someya 1, K. Tobita 1, N. Ohno
More informationToward the Realization of Fusion Energy
Toward the Realization of Fusion Energy Nuclear fusion is the energy source of the sun and stars, in which light atomic nuclei fuse together, releasing a large amount of energy. Fusion power can be generated
More informationAdaptation of Pb-Bi Cooled, Metal Fuel Subcritical Reactor for Use with a Tokamak Fusion Neutron Source
Adaptation of Pb-Bi Cooled, Metal Fuel Subcritical Reactor for Use with a Tokamak Fusion Neutron Source E. Hoffman, W. Stacey, G. Kessler, D. Ulevich, J. Mandrekas, A. Mauer, C. Kirby, D. Stopp, J. Noble
More informationImproved RF Actuator Schemes for the Lower Hybrid and the Ion Cyclotron Range of Frequencies in Reactor-Relevant Plasmas
Improved RF Actuator Schemes for the Lower Hybrid and the Ion Cyclotron Range of Frequencies in Reactor-Relevant Plasmas P. T. Bonoli*, S. G. Baek, B. LaBombard, K. Filar, M. Greenwald, R. Leccacorvi,
More informationComparing Different Scalings of Parallel Heat Flux with Toroidal Magnetic Field [q with BT] M.L. Reinke. February, 2018
PSFC/RR-18-4 Comparing Different Scalings of Parallel Heat Flux with Toroidal Magnetic Field [q with BT] M.L. Reinke February, 2018 Plasma Science and Fusion Center Massachusetts Institute of Technology
More informationThe High-Field Path to Practical Fusion Energy
The High-Field Path to Practical Fusion Energy M. Greenwald, D. Whyte, P. Bonoli, D. Brunner, Z. Hartwig, J. Irby, B. LaBombard, E. Marmar, J. Minervini, R. Mumgaard, B. Sorbom, M. Takayasu, J. Terry,
More informationCompact, spheromak-based pilot plants for the demonstration of net-gain fusion power
Compact, spheromak-based pilot plants for the demonstration of net-gain fusion power Derek Sutherland HIT-SI Research Group University of Washington July 25, 2017 D.A. Sutherland -- EPR 2017, Vancouver,
More informationComparison of tungsten fuzz growth in Alcator C-Mod and linear plasma devices!
Comparison of tungsten fuzz growth in Alcator C-Mod and linear plasma devices G.M. Wright 1, D. Brunner 1, M.J. Baldwin 2, K. Bystrov 3, R. Doerner 2, B. LaBombard 1, B. Lipschultz 1, G. de Temmerman 3,
More informationIssues for Neutron Calculations for ITER Fusion Reactor
Introduction Issues for Neutron Calculations for ITER Fusion Reactor Erik Nonbøl and Bent Lauritzen Risø DTU, National Laboratory for Sustainable Energy Roskilde, Denmark Outline 1. Fusion development
More informationImpact of High Field & High Confinement on L-mode-Edge Negative Triangularity Tokamak (NTT) Reactor
Impact of High Field & High Confinement on L-mode-Edge Negative Triangularity Tokamak (NTT) Reactor M. Kikuchi, T. Takizuka, S. Medvedev, T. Ando, D. Chen, J.X. Li, M. Austin, O. Sauter, L. Villard, A.
More informationYuntao, SONG ( ) and Satoshi NISHIO ( Japan Atomic Energy Research Institute
Conceptual design of liquid metal cooled power core components for a fusion power reactor Yuntao, SONG ( ) and Satoshi NISHIO ( Japan Atomic Energy Research Institute Japan-US workshop on Fusion Power
More informationFusion Nuclear Science (FNS) Mission & High Priority Research
Fusion Nuclear Science (FNS) Mission & High Priority Research Topics Martin Peng, Aaron Sontag, Steffi Diem, John Canik, HM Park, M. Murakami, PJ Fogarty, Mike Cole ORNL 15 th International Spherical Torus
More informationITER operation. Ben Dudson. 14 th March Department of Physics, University of York, Heslington, York YO10 5DD, UK
ITER operation Ben Dudson Department of Physics, University of York, Heslington, York YO10 5DD, UK 14 th March 2014 Ben Dudson Magnetic Confinement Fusion (1 of 18) ITER Some key statistics for ITER are:
More informationMaterial, Design, and Cost Modeling for High Performance Coils. L. Bromberg, P. Titus MIT Plasma Science and Fusion Center ARIES meeting
Material, Design, and Cost Modeling for High Performance Coils L. Bromberg, P. Titus MIT Plasma Science and Fusion Center ARIES meeting Tokamak Concept Improvement Cost minimization Decrease cost of final
More informationNuclear Energy in the Future. The ITER Project. Brad Nelson. Chief Engineer, US ITER. Presentation for NE-50 Symposium on the Future of Nuclear Energy
Nuclear Energy in the Future The ITER Project Brad Nelson Chief Engineer, US ITER Presentation for NE-50 Symposium on the Future of Nuclear Energy November 1, 2012 Fusion research is ready for the next
More informationarxiv: v1 [physics.plasm-ph] 10 Sep 2014
ARC: A compact, high-field, fusion nuclear science facility and demonstration power plant with demountable magnets B.N. Sorbom, J. Ball, T.R. Palmer, F.J. Mangiarotti, J.M. Sierchio, P. Bonoli, C. Kasten,
More informationExhaust scenarios. Alberto Loarte. Plasma Operation Directorate ITER Organization. Route de Vinon sur Verdon, St Paul lez Durance, France
Exhaust scenarios Alberto Loarte Plasma Operation Directorate ITER Organization Route de Vinon sur Verdon, 13067 St Paul lez Durance, France Acknowledgements: Members of ITER Organization (especially R.
More informationMagnetic Confinement Fusion-Status and Challenges
Chalmers energy conference 2012 Magnetic Confinement Fusion-Status and Challenges F. Wagner Max-Planck-Institute for Plasma Physics, Greifswald Germany, EURATOM Association RLPAT St. Petersburg Polytechnic
More informationHeat Flux Management via Advanced Magnetic Divertor Configurations and Divertor Detachment.
Heat Flux Management via Advanced Magnetic Divertor Configurations and Divertor Detachment E. Kolemen a, S.L. Allen b, B.D. Bray c, M.E. Fenstermacher b, D.A. Humphreys c, A.W. Hyatt c, C.J. Lasnier b,
More informationNeutronics analysis of inboard shielding capability for a DEMO fusion reactor
*Manuscript Click here to view linked References Neutronics analysis of inboard shielding capability for a DEMO fusion reactor Songlin Liu a, Jiangang Li a, Shanliang Zheng b, Neil Mitchell c a Institute
More informationOverview of Pilot Plant Studies
Overview of Pilot Plant Studies and contributions to FNST Jon Menard, Rich Hawryluk, Hutch Neilson, Stewart Prager, Mike Zarnstorff Princeton Plasma Physics Laboratory Fusion Nuclear Science and Technology
More informationFusion Nuclear Science - Pathway Assessment
Fusion Nuclear Science - Pathway Assessment C. Kessel, PPPL ARIES Project Meeting, Bethesda, MD July 29, 2010 Basic Flow of FNS-Pathways Assessment 1. Determination of DEMO/power plant parameters and requirements,
More informationStudies of Lower Hybrid Range of Frequencies Actuators in the ARC Device
Studies of Lower Hybrid Range of Frequencies Actuators in the ARC Device P. T. Bonoli, Y. Lin. S. Shiraiwa, G. M. Wallace, J. C. Wright, and S. J. Wukitch MIT PSFC, Cambridge, MA 02139 59th Annual Meeting
More informationFusion Nuclear Science Facility (FNSF) Divertor Plans and Research Options
Fusion Nuclear Science Facility (FNSF) Divertor Plans and Research Options A.M. Garofalo, T. Petrie, J. Smith, V. Chan, R. Stambaugh (General Atomics) J. Canik, A. Sontag, M. Cole (Oak Ridge National Laboratory)
More informationThe Path to Fusion Energy creating a star on earth. S. Prager Princeton Plasma Physics Laboratory
The Path to Fusion Energy creating a star on earth S. Prager Princeton Plasma Physics Laboratory The need for fusion energy is strong and enduring Carbon production (Gton) And the need is time urgent Goal
More informationTokamak Divertor System Concept and the Design for ITER. Chris Stoafer April 14, 2011
Tokamak Divertor System Concept and the Design for ITER Chris Stoafer April 14, 2011 Presentation Overview Divertor concept and purpose Divertor physics General design considerations Overview of ITER divertor
More informationWhich Superconducting Magnets for DEMO and Future Fusion Reactors?
Which Superconducting Magnets for DEMO and Future Fusion Reactors? Reinhard Heller Inspired by Jean Luc Duchateau (CEA) INSTITUTE FOR TECHNICAL PHYSICS, FUSION MAGNETS KIT University of the State of Baden-Wuerttemberg
More informationPSI meeting, Aachen Germany, May 2012
Constraining the divertor heat width in ITER D.G. Whyte 1, B. LaBombard 1, J.W. Hughes 1, B. Lipschultz 1, J. Terry 1, D. Brunner 1, P.C. Stangeby 2, D. Elder 2, A.W. Leonard 3, J. Watkins 4 1 MIT Plasma
More informationGA A23168 TOKAMAK REACTOR DESIGNS AS A FUNCTION OF ASPECT RATIO
GA A23168 TOKAMAK REACTOR DESIGNS AS A FUNCTION OF ASPECT RATIO by C.P.C. WONG and R.D. STAMBAUGH JULY 1999 DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United
More informationDiagnostics for Burning Plasma Physics Studies: A Status Report.
Diagnostics for Burning Plasma Physics Studies: A Status Report. Kenneth M. Young Princeton Plasma Physics Laboratory UFA Workshop on Burning Plasma Science December 11-13 Austin, TX Aspects of Plasma
More informationEU PPCS Models C & D Conceptual Design
Institut für Materialforschung III EU PPCS Models C & D Conceptual Design Presented by P. Norajitra, FZK 1 PPCS Design Studies Strategy definition [D. Maisonnier] 2 models with limited extrapolations Model
More informationDesign window analysis of LHD-type Heliotron DEMO reactors
Design window analysis of LHD-type Heliotron DEMO reactors Fusion System Research Division, Department of Helical Plasma Research, National Institute for Fusion Science Takuya GOTO, Junichi MIYAZAWA, Teruya
More informationThe Spherical Tokamak as a Compact Fusion Reactor Concept
The Spherical Tokamak as a Compact Fusion Reactor Concept R. Kaita Princeton Plasma Physics Laboratory ENN Symposium on Compact Fusion Technologies April 19 20, 2018 *This work supported by US DOE Contract
More informationDrift-Driven and Transport-Driven Plasma Flow Components in the Alcator C-Mod Boundary Layer
Drift-Driven and Transport-Driven Plasma Flow Components in the Alcator C-Mod Boundary Layer N. Smick, B. LaBombard MIT Plasma Science and Fusion Center PSI-19 San Diego, CA May 25, 2010 Boundary flows
More informationComparison of tungsten fuzz growth in Alcator C-Mod and linear plasma devices
Comparison of tungsten fuzz growth in Alcator C-Mod and linear plasma devices G.M. Wright 1, D. Brunner 1, M.J. Baldwin 2, K. Bystrov 3, R. Doerner 2, B. LaBombard 1, B. Lipschultz 1, G. de Temmerman 3,
More informationDesign concept of near term DEMO reactor with high temperature blanket
Design concept of near term DEMO reactor with high temperature blanket Japan-US Workshop on Fusion Power Plants and Related Advanced Technologies March 16-18, 2009 Tokyo Univ. Mai Ichinose, Yasushi Yamamoto
More informationHT-7U* Superconducting Tokamak: Physics design, engineering progress and. schedule
1 FT/P2-03 HT-7U* Superconducting Tokamak: Physics design, engineering progress and schedule Y.X. Wan 1), P.D. Weng 1), J.G. Li 1), Q.Q. Yu 1), D.M. Gao 1), HT-7U Team 1) Institute of Plasma Physics, Chinese
More informationNeutron Testing: What are the Options for MFE?
Neutron Testing: What are the Options for MFE? L. El-Guebaly Fusion Technology Institute University of Wisconsin - Madison http://fti.neep.wisc.edu/uwneutronicscenterofexcellence Contributors: M. Sawan
More informationAspects of Advanced Fuel FRC Fusion Reactors
Aspects of Advanced Fuel FRC Fusion Reactors John F Santarius and Gerald L Kulcinski Fusion Technology Institute Engineering Physics Department CT2016 Irvine, California August 22-24, 2016 santarius@engr.wisc.edu;
More informationMaterials for Future Fusion Reactors under Severe Stationary and Transient Thermal Loads
Mitglied der Helmholtz-Gemeinschaft Materials for Future Fusion Reactors under Severe Stationary and Transient Thermal Loads J. Linke, J. Du, N. Lemahieu, Th. Loewenhoff, G. Pintsuk, B. Spilker, T. Weber,
More informationHelium Catalyzed D-D Fusion in a Levitated Dipole
Helium Catalyzed D-D Fusion in a Levitated Dipole Jay Kesner, L. Bromberg, MIT D.T. Garnier, A. Hansen, M.E. Mauel Columbia University APS 2003 DPP Meeting, Albuquerque October 27, 2003 Columbia University
More informationEffect of divertor nitrogen seeding on the power exhaust channel width in Alcator C-Mod
Effect of divertor nitrogen seeding on the power exhaust channel width in Alcator C-Mod B. LaBombard, D. Brunner, A.Q. Kuang, W. McCarthy, J.L. Terry and the Alcator Team Presented at the International
More informationDer Stellarator Ein alternatives Einschlusskonzept für ein Fusionskraftwerk
Max-Planck-Institut für Plasmaphysik Der Stellarator Ein alternatives Einschlusskonzept für ein Fusionskraftwerk Robert Wolf robert.wolf@ipp.mpg.de www.ipp.mpg.de Contents Magnetic confinement The stellarator
More informationFusion Development Facility (FDF) Divertor Plans and Research Options
Fusion Development Facility (FDF) Divertor Plans and Research Options A.M. Garofalo, T. Petrie, J. Smith, M. Wade, V. Chan, R. Stambaugh (General Atomics) J. Canik (Oak Ridge National Laboratory) P. Stangeby
More informationMacroscopic Stability
Macroscopic Stability FESAC Facilities Panel Meeting June 13, 2005 E. S. Marmar for the Alcator Group Unique C-Mod Properties Guide MHD Research Program High field, high current density, compact size,
More informationUS-Japan workshop on Fusion Power Reactor Design and Related Advanced Technologies, March at UCSD.
US-Japan workshop on Fusion Power Reactor Design and Related Advanced Technologies, March 5-7 28 at UCSD. Overview Overview of of Design Design Integration Integration toward toward Optimization -type
More informationSpherical Torus Fusion Contributions and Game-Changing Issues
Spherical Torus Fusion Contributions and Game-Changing Issues Spherical Torus (ST) research contributes to advancing fusion, and leverages on several game-changing issues 1) What is ST? 2) How does research
More informationPower balance of Lower Hybrid Current Drive in the SOL of High Density Plasmas on Alcator C-Mod
Power balance of Lower Hybrid Current Drive in the SOL of High Density Plasmas on Alcator C-Mod I.C. Faust, G.M. Wallace, S.G. Baek, D. Brunner, B. LaBombard, R.R. Parker, Y. Lin, S. Shiraiwa, J.L. Terry,
More informationPerspective on Fusion Energy
Perspective on Fusion Energy Mohamed Abdou Distinguished Professor of Engineering and Applied Science (UCLA) Director, Center for Energy Science & Technology (UCLA) President, Council of Energy Research
More informationTHE OPTIMAL TOKAMAK CONFIGURATION NEXT-STEP IMPLICATIONS
THE OPTIMAL TOKAMAK CONFIGURATION NEXT-STEP IMPLICATIONS by R.D. STAMBAUGH Presented at the Burning Plasma Workshop San Diego, California *Most calculations reported herein were done by Y-R. Lin-Liu. Work
More informationProspects of Nuclear Fusion Energy Research in Lebanon and the Middle-East
Prospects of Nuclear Fusion Energy Research in Lebanon and the Middle-East Ghassan Antar Physics Department American University of Beirut http://www.aub.edu.lb/physics/lpfd Outline 1. Introduction and
More informationIs the Troyon limit a beta limit?
Is the Troyon limit a beta limit? Pierre-Alexandre Gourdain 1 1 Extreme State Physics Laboratory, Department of Physics and Astronomy, University of Rochester, Rochester, NY 14627, USA The plasma beta,
More informationMission and Design of the Fusion Ignition Research Experiment (FIRE)
Mission and Design of the Fusion Ignition Research Experiment (FIRE) D. M. Meade 1), S. C. Jardin 1), J. A. Schmidt 1), R. J. Thome 2), N. R. Sauthoff 1), P. Heitzenroeder 1), B. E. Nelson 3), M. A. Ulrickson
More informationI-mode and H-mode plasmas at high magnetic field and pressure on Alcator C-Mod
I-mode and H-mode plasmas at high magnetic field and pressure on Alcator C-Mod A. E. Hubbard, J. W Hughes, S.-G. Baek, D. Brunner, I. Cziegler 1, E. Edlund, T. Golfinopoulos, M.J. Greenwald, J. Irby, B.
More informationINTRODUCTION TO MAGNETIC NUCLEAR FUSION
INTRODUCTION TO MAGNETIC NUCLEAR FUSION S.E. Sharapov Euratom/CCFE Fusion Association, Culham Science Centre, Abingdon, Oxfordshire OX14 3DB, UK With acknowledgments to B.Alper for use of his transparencies
More informationScrape Off Layer Physics for Burning Plasmas and Innovative Divertor Solutions
1 IC/P6-43 Scrape Off Layer Physics for Burning Plasmas and Innovative Divertor Solutions M. Kotschenreuther 1), P. Valanju 1), J. Wiley 1), T. Rognlein 2), S. Mahajan 1), and M. Pekker 1) 1) Institute
More informationfor the French fusion programme
The ITER era : the 10 year roadmap for the French fusion programme E. Tsitrone 1 on behalf of IRFM and Tore Supra team 1 : CEA, IRFM, F-13108 Saint-Paul-lez-Durance, France Association EURATOM-CEA TORE
More informationAtomic physics in fusion development
Atomic physics in fusion development The next step in fusion development imposes new requirements on atomic physics research by R.K. Janev In establishing the scientific and technological base of fusion
More informationFusion/transmutation reactor studies based on the spherical torus concept
FT/P1-7, FEC 2004 Fusion/transmutation reactor studies based on the spherical torus concept K.M. Feng, J.H. Huang, B.Q. Deng, G.S. Zhang, G. Hu, Z.X. Li, X.Y. Wang, T. Yuan, Z. Chen Southwestern Institute
More informationPHYSICS OF CFETR. Baonian Wan for CFETR physics group Institute of Plasma Physcis, Chinese Academy of Sciences, Hefei, China.
PHYSICS OF CFETR Baonian Wan for CFETR physics group Institute of Plasma Physcis, Chinese Academy of Sciences, Hefei, China Dec 4, 2013 Mission of CFETR Complementary with ITER Demonstration of fusion
More informationOverview of edge modeling efforts for advanced divertor configurations in NSTX-U with magnetic perturbation fields
Overview of edge modeling efforts for advanced divertor configurations in NSTX-U with magnetic perturbation fields H. Frerichs, O. Schmitz, I. Waters, G. P. Canal, T. E. Evans, Y. Feng and V. Soukhanovskii
More informationStatus of the Concept Design of CFETR Tokamak Machine
Status of the Concept Design of CFETR Tokamak Machine Tokamak Machine Design Team Presented by Songtao WU Slide 1 Outline Guideline of the Tokamak Design Magnet Configuration and Preliminary Analysis VV
More informationPlasma Wall Interactions in Tokamak
Plasma Wall Interactions in Tokamak Dr. C Grisolia, Association Euratom/CEA sur la fusion, CEA/Cadarache Outline 1. Conditions for Fusion in Tokamaks 2. Consequences of plasma operation on in vessel materials:
More informationElectrical Resistivity Changes with Neutron Irradiation and Implications for W Stabilizing Shells
Electrical Resistivity Changes with Neutron Irradiation and Implications for W Stabilizing Shells L. El-Guebaly Fusion Technology Institute University of Wisconsin-Madison With input from: C. Kessel (PPPL)
More information(Inductive tokamak plasma initial start-up)
(Inductive tokamak plasma initial start-up) 24. 6. 7. (tapl1.kaist.ac.kr) Outline Conventional inductive tokamak plasma start-up Inductive outer PF coil-only plasma start-up Inductive plasma start-up in
More informationCross-Field Plasma Transport and Main Chamber Recycling in Diverted Plasmas on Alcator C-Mod
Cross-Field Plasma Transport and Main Chamber Recycling in Diverted Plasmas on Alcator C-Mod B. LaBombard, M. Umansky, R.L. Boivin, J.A. Goetz, J. Hughes, B. Lipschultz, D. Mossessian, C.S. Pitcher, J.L.Terry,
More informationSteady State, Transient and Off-Normal Heat Loads in ARIES Power Plants
Steady State, Transient and Off-Normal Heat Loads in ARIES Power Plants C. E. Kessel 1, M. S. Tillack 2, and J. P. Blanchard 3 1 Princeton Plasma Physics Laboratory 2 University of California, San Diego
More informationTechnological and Engineering Challenges of Fusion
Technological and Engineering Challenges of Fusion David Maisonnier and Jim Hayward EFDA CSU Garching (david.maisonnier@tech.efda.org) 2nd IAEA TM on First Generation of FPP PPCS-KN1 1 Outline The European
More informationScaling of divertor heat flux profile widths in DIII-D
1 Scaling of divertor heat flux profile widths in DIII-D C.J. Lasnier 1, M.A. Makowski 1, J.A. Boedo 2, N.H. Brooks 3, D.N. Hill 1, A.W. Leonard 3, and J.G. Watkins 4 e-mail:lasnier@llnl.gov 1 Lawrence
More informationImproved Magnetic Fusion Energy Economics Via Massive Resistive Electromagnets
Improved Magnetic Fusion Energy Economics Via Massive Resistive Electromagnets Robert D. Woolley Princeton University Princeton Plasma Physics Laboratory* P.O. Box 451 Princeton, New Jersey 08543 (609)
More informationAttainment of a stable, fully detached plasma state in innovative divertor configurations
Attainment of a stable, fully detached plasma state in innovative divertor configurations M.V. Umansky, Lawrence, Livermore National Laboratory, Livermore, CA 94550, USA O. Izacard, M.E. Rensink, T.D.
More informationConsideration on Design Window for a DEMO Reactor
Japan-US Workshop on Fusion Power Plants and Related Advanced Technologies with participation of China March 16-18, 2009 at the University of Tokyo in Kashiwa, JAPAN Consideration on Design Window for
More information3.12 Development of Burn-up Calculation System for Fusion-Fission Hybrid Reactor
3.12 Development of Burn-up Calculation System for Fusion-Fission Hybrid Reactor M. Matsunaka, S. Shido, K. Kondo, H. Miyamaru, I. Murata Division of Electrical, Electronic and Information Engineering,
More informationPower Balance and Scaling of the Radiated Power in the Divertor and Main Plasma of Alcator C-Mod
PFC/JA-94-15 Power Balance and Scaling of the Radiated Power in the Divertor and Main Plasma of Alcator C-Mod J.A. Goetz, B. Lipschultz, M.A. Graf, C. Kurz, R. Nachtrieb, J.A. Snipes, J.L. Terry Plasma
More informationDirect drive by cyclotron heating can explain spontaneous rotation in tokamaks
Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks J. W. Van Dam and L.-J. Zheng Institute for Fusion Studies University of Texas at Austin 12th US-EU Transport Task Force Annual
More informationDeveloping Steady State ELM-absent H-Mode scenarios with Advanced Divertor Configuration in EAST tokamak
Developing Steady State ELM-absent H-Mode scenarios with Advanced Divertor Configuration in EAST tokamak G. Calabrò, B.J. Xiao, J.G. Li, Z.P. Luo, Q.P. Yuan, L. Wang, K. Wu, R. Albanese, R. Ambrosino,
More informationConceptual Design of CFETR Tokamak Machine
Japan-US Workshop on Fusion Power Plants and Related Advanced Technologies February 26-28, 2013 at Kyoto University in Uji, JAPAN Conceptual Design of CFETR Tokamak Machine Yuntao Song for CFETR Design
More informationProgress on developing the spherical tokamak for fusion applications
Progress on developing the spherical tokamak for fusion applications Jonathan Menard 1 T. Brown 1, J. Canik 2, J. Chrzanowski 1, L. Dudek 1, L. El Guebaly 3, S. Gerhardt 1, S. Kaye 1, C. Kessel 1, E. Kolemen
More informationELECTROMAGNETIC LIQUID METAL WALL PHENOMENA
ELECTROMAGNETIC LIQUID METAL WALL PHENOMENA BY BOB WOOLLEY 15-19 FEBRUARY 1999 APEX-6 MEETING LIQUID WALLS A sufficiently thick, flowing, liquid first wall and tritium breeding blanket which almost completely
More informationMagnetic Confinement Fusion and Tokamaks Chijin Xiao Department of Physics and Engineering Physics University of Saskatchewan
The Sun Magnetic Confinement Fusion and Tokamaks Chijin Xiao Department of Physics and Engineering Physics University of Saskatchewan 2017 CNS Conference Niagara Falls, June 4-7, 2017 Tokamak Outline Fusion
More informationTransmutation of Minor Actinides in a Spherical
1 Transmutation of Minor Actinides in a Spherical Torus Tokamak Fusion Reactor Feng Kaiming Zhang Guoshu Fusion energy will be a long-term energy source. Great efforts have been devoted to fusion research
More informationDriving Mechanism of SOL Plasma Flow and Effects on the Divertor Performance in JT-60U
EX/D-3 Driving Mechanism of SOL Plasma Flow and Effects on the Divertor Performance in JT-6U N. Asakura ), H. Takenaga ), S. Sakurai ), G.D. Porter ), T.D. Rognlien ), M.E. Rensink ), O. Naito ), K. Shimizu
More informationTHE ADVANCED TOKAMAK DIVERTOR
I Department of Engineering Physics THE ADVANCED TOKAMAK DIVERTOR S.L. Allen and the team 14th PSI QTYUIOP MA D S O N UCLAUCLA UCLA UNIVERSITY OF WISCONSIN THE ADVANCED TOKAMAK DIVERTOR S.L. Allen and
More information