Electromagnetic Interaction of the Blanket and the Plasma

Slides:



Advertisements
Similar presentations
November 3-5, 2003Feedback Workshop, Austin NORMAL MODE APPROACH TO MODELING OF FEEDBACK STABILIZATION OF THE RESISTIVE WALL MODE By M.S. Chu(GA), M.S.
Advertisements

Seminario UT FUSIONE Aula Brunelli, Centro Ricerche Frascati 8 Febbraio 2010 Ideal MHD Stability Boundaries of the PROTO-SPHERA Configuration F. Alladio,
First Wall Heat Loads Mike Ulrickson November 15, 2014.
West Lake International Symposium on Plasma Simulation; April, 2012 Influence of magnetic configuration on kinetic damping of the resistive wall.
Halo Current and Resistive Wall Simulations of ITER H.R. Strauss 1, Linjin Zheng 2, M. Kotschenreuther 2, W.Park 3, S. Jardin 3, J. Breslau 3, A.Pletzer.
ICC2004 Madison, Wisconsin The Multi-Pinch Experiment Outline PROTO-SPHERA purpose & aims Theoretical basis & analysis Multi-Pinch: a step towards PROTO-SPHERA.
Who will save the tokamak – Harry Potter, Arnold Schwarzenegger, Shaquille O’Neal or Donald Trump? J. P. Freidberg, F. Mangiarotti, J. Minervini MIT Plasma.
Study on supporting structures of magnets and blankets for a heliotron-type fusion reactors Study on supporting structures of magnets and blankets for.
January 8-10, 2003/ARR 1 Plan for Engineering Study of ARIES-CS Presented by A. R. Raffray University of California, San Diego ARIES Meeting UCSD San.
September 3-4, 2003/ARR 1 Initial Assessment of Maintenance Scheme for 2- Field Period Configuration A. R. Raffray X. Wang University of California, San.
Physics Analysis for Equilibrium, Stability, and Divertors ARIES Power Plant Studies Charles Kessel, PPPL DOE Peer Review, UCSD August 17, 2000.
Physics of fusion power
Physics of fusion power Lecture 4: Cylindrical concepts.
Magnet System Definition L. Bromberg P. Titus MIT Plasma Science and Fusion Center ARIES meeting November 4-5, 2004.
Proposals for Next Year’s MFE Activities C. Kessel, PPPL ARIES Project Meeting, Sept. 24, 2000.
Development of the New ARIES Tokamak Systems Code Zoran Dragojlovic, Rene Raffray, Farrokh Najmabadi, Charles Kessel, Lester Waganer US-Japan Workshop.
LOCA/LOFA Analyses for Blanket and Shield Only Regions – LiPb/FS/He System Carl Martin, Jake Blanchard Fusion Technology Institute University of Wisconsin.
Highlights of ARIES-AT Study Farrokh Najmabadi For the ARIES Team VLT Conference call July 12, 2000 ARIES Web Site:
Status of the ARIES-CS Power Core Configuration and Maintenance Presented by X.R. Wang Contributors: S. Malang, A.R. Raffray ARIES Meeting PPPL, NJ Sept.
Thermofluid MHD issues for liquid breeder blankets and first walls Neil B. Morley and Sergey Smolentsev MAE Dept., UCLA APEX/TBM Meeting November 3, 2003.
Physics of fusion power Lecture 2: Lawson criterion / some plasma physics.
Physics of Fusion power Lecture4 : Quasi-neutrality Force on the plasma.
1 MHD for Fusion Where to Next? Jeff Freidberg MIT.
In Engineering --- Designing a Pneumatic Pump Introduction System characterization Model development –Models 1, 2, 3, 4, 5 & 6 Model analysis –Time domain.
Kaschuck Yu.A., Krasilnikov A.V., Prosvirin D.V., Tsutskikh A.Yu. SRC RF TRINITI, Troitsk, Russia Status of the divertor neutron flux monitor design and.
Advanced Tokamak Plasmas and the Fusion Ignition Research Experiment Charles Kessel Princeton Plasma Physics Laboratory Spring APS, Philadelphia, 4/5/2003.
Perspectives of tearing modes control in RFX-mod Paolo Zanca Consorzio RFX, Associazione Euratom-ENEA sulla Fusione, Padova, Italy.
Kinetic Effects on the Linear and Nonlinear Stability Properties of Field- Reversed Configurations E. V. Belova PPPL 2003 APS DPP Meeting, October 2003.
Hybrid Simulations of Energetic Particle-driven Instabilities in Toroidal Plasmas Guo-Yong Fu In collaboration with J. Breslau, J. Chen, E. Fredrickson,
October 27-28, 2004 HAPL meeting, PPPL 1 Thermal-Hydraulic Analysis of Ceramic Breeder Blanket and Plan for Future Effort A. René Raffray UCSD With contributions.
The efficient sustainment of a stable, high-β spheromak: modeling By Tom Jarboe, To PSI-Center July 29, 2015.
Stability Properties of Field-Reversed Configurations (FRC) E. V. Belova PPPL 2003 International Sherwood Fusion Theory Conference Corpus Christi, TX,
Current Drive for FIRE AT-Mode T.K. Mau University of California, San Diego Workshop on Physics Issues for FIRE May 1-3, 2000 Princeton Plasma Physics.
Resonant magnetic perturbation effect on the tearing mode dynamics in EXTRAP T2R: experimental results and modeling L. Frassinetti, K.E.J. Olofsson, P.R.
ARIES-AT Physics Overview presented by S.C. Jardin with input from C. Kessel, T. K. Mau, R. Miller, and the ARIES team US/Japan Workshop on Fusion Power.
DIII-D SHOT #87009 Observes a Plasma Disruption During Neutral Beam Heating At High Plasma Beta Callen et.al, Phys. Plasmas 6, 2963 (1999) Rapid loss of.
Nonlinear interactions between micro-turbulence and macro-scale MHD A. Ishizawa, N. Nakajima, M. Okamoto, J. Ramos* National Institute for Fusion Science.
Stabilizing Shells in ARIES C. E. Kessel Princeton Plasma Physics Laboratory ARIES Project Meeting, 5/28-29/2008.
Magnet for ARIES-CS Magnet protection Cooling of magnet structure L. Bromberg J.H. Schultz MIT Plasma Science and Fusion Center ARIES meeting UCSD January.
Characteristics of Transmutation Reactor Based on LAR Tokamak Neutron Source B.G. Hong Chonbuk National University.
The influence of non-resonant perturbation fields: Modelling results and Proposals for TEXTOR experiments S. Günter, V. Igochine, K. Lackner, Q. Yu IPP.
Some slides on UCLA LM-MHD capabilities and Preliminary Incompressible LM Jet Simulations in Muon Collider Fields Neil Morley and Manmeet Narula Fusion.
ASIPP Magnetic Diagnostics of HT-7U Tokamak Shen Biao Wan Baonian Institute of Plasma Physics, CAS P.O.Box 1126, Hefei, Anhui , P.R.China (e_mail:
Numerical Study on Ideal MHD Stability and RWM in Tokamaks Speaker: Yue Liu Dalian University of Technology, China Co-Authors: Li Li, Xinyang Xu, Chao.
Advanced Tokamak Modeling for FIRE C. Kessel, PPPL NSO/PAC Meeting, University of Wisconsin, July 10-11, 2001.
Energetic ion excited long-lasting “sword” modes in tokamak plasmas with low magnetic shear Speaker:RuiBin Zhang Advisor:Xiaogang Wang School of Physics,
NIMROD Simulations of a DIII-D Plasma Disruption S. Kruger, D. Schnack (SAIC) April 27, 2004 Sherwood Fusion Theory Meeting, Missoula, MT.
Compact Stellarators as Reactors J. F. Lyon, ORNL NCSX PAC meeting June 4, 1999.
Design of a feedback control system for KTX Hong Li, on behalf of KTX team The 17th International RFP Workshop, October , 2015, Hefei 1.
Systems Analysis of D-T and D- 3 He FRC Power Plants J.F. Santarius, S.V. Ryzhkov †, C.N. Nguyen ‡, and G.A. Emmert University of Wisconsin L.C. Steinhauer.
Unstructured Meshing Tools for Fusion Plasma Simulations
Equilibrium and Stability
PHYS 1444 – Section 501 Lecture #16
Produktentwicklung und Maschinenelemente
Huishan Cai, Jintao Cao, Ding Li
Can We achieve the TBR Needed in FNF?
University of California, San Diego
Lecture 0: Introduction to Engineering Electromagnetics
UPDATE ON  LIMITS FOR ARIES-CS
Physics of fusion power
Influence of energetic ions on neoclassical tearing modes
Comparison of CFEM and DG methods
New Development in Plasma and Coil Configurations
ARIES-CS Project Meeting Princeton Plasma Physics Laboratory, NJ
EEM476 Power Electronics II
IV–2 Inductance
Analysis of Technical and Programmatic Tradeoffs with Systems Code
Stellarator Program Update: Status of NCSX & QPS
University of California, San Diego
Presentation transcript:

Electromagnetic Interaction of the Blanket and the Plasma Investigators M. Kotschenreuther, L. Zheng, J. Wiley IFS: University of Texas Institute for Fusion Studies

Reactor Blankets- even more than Neutronics, Thermo-Hydraulics, Structural Mechanics, … Reactor blankets are also expected to aid in tokamak plasma MHD stability Attractive reactors with low current drive and high beta need wall stabilization Usually thought of as an after-thought: “just” add a conducting shell However, there is considerable metallic conductivity in the engineering blanket itself In principle, this could either: Enhance the stability of the plasma Interfere with the stabilizing effect of the nominal shell

Blanket Effects on Plasma Stability are Substantial Initial calculations find: The conductivity in the blanket often suffices to eliminate the need for a dedicated conducting shell for kink modes Expect this to improve breeding ratio Simplify reactor design The conductivity in the blanket or neutron shield interferes with stability by: Neutron shield of steel can also electromagnetically shield necessary feedback signals from the plasma Must laminate the shield to reduce eddy currents The blanket puts conductivity “too close” to the plasma- preventing stabilization from plasma rotation Plasma rotation is thus not viable for stabilizing low n MHD wall modes in a reactor- feedback MUST be used Ferritic effects on plasma stability are not large Since ambient magnetic field is well beyond saturation

Blanket Types and Characteristics Have considered following types of blankets so far: Stationary “Pool” blankets of liquid LiPb- no insulators E.g., He or water cooled Flowing LiPb in insulated poloidal channels with steel structure Have considered toroidally segmented blanket modules- Assumed 16 blanket segments here Each segment is assumed electrically isolated How much electrical connection is there between segments, e.g., welded to vacuum vessel at back?

Blanket Models Blanket is a very complex electrical structure- two models are being developed: Use simplified average response model here Isolated eddy currrents inside insulated LiPb channels are included Eddy currents from steel structure are included Note: overall impact of LiPb currents often exceeds steel currents Assume all structures have spatial scale less than inductive field so can average and obtain smooth PDE’s Straightforward analysis is then possible using standard methods, but still accounting for blanket complexity Approximations marginal because channels are not that small Detailed finite element model of the blanket Very similar code already developed at IFS for other EM response applications Modification for present application – several months Very detailed analysis possible In both models, PbLi flow is assumed unperturbed (so far)

Coupling to the Plasma For realistic plasma equilibria- use AEGIS Benchmarked against GATO for elongated, triangular geometries Committed to results by IAEA (November) for average response model Results from finite element model probably on roughly same time scale Today- simplified circular cross section geometry for initial results Model commonly used within plasma community for first investigations of resistive wall mode effects Several conclusions expected to be robust and apply to more realistic cases

Consider Stabilization of Resistive Wall Kink Modes Use same gross parameters as ARIES AT Same shell (1 cm W for kinks) Same distance of shell from plasma Plasma instabilities with same stabilization distance for ideal shell (toroidal mode numbers n=1-4) Note: ARIES analysis (RS,AT,ST) – ignored effects of blanket conductivity We immerse this shell in a flowing LiPb blanket Similar to ARIES ST: poloidal channels 0.25m x 0.25 m 0.75 m thick RESULTS: Addition of blanket reduces resistive instability growth rate by ~ 3 times Without W shell, blanket alone gives instability growth rate ~1.5 - 2 times less than shell alone A dedicated kink mode shell is unnecessary Breeding ratio and design simplicity improved Reduced growth rates can enhance prospects for feedback stabilization The eddy currents in the PbLi contribute more than steel

Deleterious Effects of the Shield on Feedback Stabilization The neutron shield can also shield the plasma from feedback signals of coils outside the shield Unless the shield (0.65) is laminated: Feedback gain requirements are increased by ~ 3-4 for mode numbers 1-2 Implies a considerable increase in feedback power Also, potential for feedback driven instabilies Need to include finite feedback bandwidth to assess this Lamination of the shield to the same degree as the blanket (0.25 m channels) greatly reduces problem With sufficient lamination, feedback stabilization of plasma resisitive wall modes (n=1-2) appears possible without an added stabilizing shell

Serious Effects of the Blanket on Stabilization by Plasma Rotation Plasma rotation is another method to stabilize plasma modes An alternative to feedback, but required plasma rotation is regarded as too high from analysis which ignore the blanket It is deleteriously effected by placing conductors too close to the plasma The blanket/steel first wall has sufficient conductivity close to the plasmas to increase rotation requirements significantly n=1 ~ 100% increase n=2 ~ 50- 100 % increase n=3 ~ 10-20% increase n=4 ~ 10 – 20 % reduction Plasma rotation appears to not be a feasible option for stabilizing n = 1-2 modes: feedback MUST be used

Effects of the Blanket on Stabilization of Axisymmetric modes (Vertical Instability) Axisymmetric stability is difficult to assess in a circular model, but some qualitative results seem robust A toroidally segmented blanket has much less effect on axi-symmetric modes than on kink modes Without a strong electrical connection between segments, a flowing Pb blanket/shield will not substantially affect shell requirements or feedback for the vertical mode A pool PbLi blanket may significantly reduce shell/feedback requirements With strong electrical connection in the back, a flowing PbLi blanket might also reduce shell/feedback requirements Satisfactory analysis of blanket effects on the axi-symmetric instability require the 3-D finite element approach (more so than kink modes)

Finite Element Model of the Blanket A finite element code to solve the full Maxwell’s equations with arbitrary conductivity and permeability has already been developed at the IFS (for RF applications) By eliminating the displacement current term, it can be fairly easily adapted for the low frequency blanket electromagnetic response Already efficiently parallelizable Algorithm: discontinuous Galerkin method Very well suited to problems with discontinuous conductivities/permeabilities (as in blankets with insulator/metal/vacuum interfaces) High order accuracy: fast convergence and fewer spurious eigenvalues found in practice Time scale for applications to this problem: a few months The code could also potentially calculate eddy currents in fast disruptions, or static magnetic perturbations from ferritics

Potential Plasma Performance Optimizations By utilizing the conductivity in metal breeder blankets, it may be possible to moderately increase plasma elongation Increasing elongation even from 1.8 to 2.2 can increase beta by almost 2 (ARIES RS to ARIES AT) Increasing elongation from 2.2 to 2.5 can increase beta to perhaps another 50%- still very useful (work by Chuck Kessel and M.K.) A more modest improvement than in APEX, but significant Increased elongation would also modestly improve confinement Thus, even conventional blankets can be utilized to improve plasma performance in novel ways Such optimizations have never been considered before because no suitable 3D code was available for analyzing the coupled plasma/blanket interaction The tools discussed would provide such a tool

Conclusions The blanket has very significant electromagnetic interactions with the plasma Cases analyzed have sufficient conductivity that an additional stabilizing shell for kink modes is unnecessary- aiding breeding Blanket interactions quite negatively affect the viability of plasma rotation stabilization for modes n = 1-2, implying feedback is needed Satisfactory feedback performance probably requires some degree of lamination of the shield Blanket effects may possibly reduce the requirement for the axisymmetric stabilizing shell-further improving breeding More quantitative results with realistic geometry and possibly a finite element treatment of the blanket expected before year end The blanket might also assist in attaining higher elongation and bettter wall stabilization which can improve reactor plasma performance