1 Nick Antonio Dez Prince May 2, 2017CONFINEMENT Nick Antonio Dez Prince May 2, 2017

2 agenda Magnetic Confinement Defined Effects on Confinement Plasma Shaping Instabilities Plasma Facing Materials Magnets ITER Performance Tokamak Symmtery Baseline Tokamaks Scaling Interpretation Shortfalls Impurities Conclusion

3 What Is MAGNETIC Confinement?“Magnetic confinement fusion is an approach to generating fusion power that uses magnetic fields (which is a magnetic influence of electric currents and magnetic materials) to confine the hot fusion fuel in the form of a plasma… Magnetic confinement fusion attempts to create the conditions needed for fusion energy production by using the electrical conductivity of the plasma to contain it with magnetic fields.” ITER’s Required Confinement Capability Magnetic confinement is of significance in that magnetic fields not only “confine” the plasma—they’re also instrumental in generating pressure and heat required for a gas to become a plasma. (http://science.howstuffworks.com/fusion-reactor3.htm) “Magnetic confinement fusion,” Wikipedia “ITER Physics,” IAEA

4 Confinement time Initially, in Chapter 3, we explored confinement time— “The length of time for which particles are confined within the plasma... One of the three critical parameters for fusion plasmas, along with temperature and number density, that form the triple product.” a, minor radius (m) – 2.0 Ro, major radius (m) – 6.2 q95, edge safety factor – 3.0 Bφ, toroidal magnetic field (T) – 5.3 Some of the parameters we might have used to determine confinement times are provided here. However, the expressions given by Equations 3.74 and 3.75 are not appropriate for ITER. Instead, we consider a factor known as energy confinement time. q95, edge safety factor -the value of the safety factor at the 95% magnetic flux surface, or the flux surface that encloses 95% of the toroidal flux International Thermonuclear Experimental Reactor (ITER) є, inverse aspect ratio (a/Ro) "Confinement Time,” EUROfusion “ITER,” FusionWiki

5 Energy Confinement timeEnergy confinement time “measures the rate at which a system loses energy to its environment.” H-mode Correlation (17.18) I, current (MA) B, toroidal magnetic field (T) n, average electron density M, atomic mass of the ions (amu) R, major plasma radius (m) κ, plasma elongation (b/a) A, aspect ratio (R/a) P, heating power (MW) Energy confinement time “measures the rate at which a system loses energy to its environment.” Energy confinement time, τE, is generically expressed the energy density W (energy content per unit volume) divided by the power loss density, Ploss (rate of energy loss per unit volume). Energy confinement time is important, because it, in part, influences whether enough fusion occurs to sustain a reaction. If the system becomes too low in energy, fusion cannot continue. (http://ippex.pppl.gov/prev_ippex/fusion/glossary.html) Robert J. Goldston was able to analyze data from several tokamaks to generate confinement scaling laws that more accurately describe what a tokamak’s energy confinement time would be. Taking into consideration these scaling laws, a series of confinement times for ITER were developed. The most recent scaling law shown here is an H-mode correlation. “Lawson Criterion,” Wikipedia Fusion Plasma Physics, Dr. Weston M. Stacey

6 Energy Confinement TimeAs you can see here, the goal of ITER is to reach an energy confinement time of 3.7 seconds, or about 4 seconds. “The Physics Basis of ITER Confinement,” F. Wagner

7 Plasma Shaping Geometric factors influencing energy confinement time— Aspect ratio, Plasma elongation, , where b is the height of the plasma measured from the equatorial plane Plasma triangularity, δ, the horizontal distance between the major radius and the x-point Some factors that directly influence energy confinement time as indicated by Equation are also related to the plasma’s geometry. These factors are κ, plasma elongation (b/a), and A, the ratio of the major radius to minor radius (R/a). Additionally, a third factor known as triangularity, δ, is also responsible for influencing plasma energy confinement time. separatrix - is the boundary separating two modes of behavior in a differential equation. “Plasma shaping,” Wikipedia “Separatrix,” FusionWiki

8 Plasma Shaping ITER’ geometry— Aspect ratio, A = 3.1 Lower aspect ratios yield increased plasma stability, kink instability suppression, and increased energy confinement time. Elongation, κsep = 1.85 Elongation, κ95 = 1.70 Allows for increased plasma current, pressure, and confinement time. Triangularity, δ sep = 0.48 Triangularity, δ 95 = 0.33 Increased triangularity is associated with an increase in pedestal pressure. Pedestal pressure is associated with the transition from L- to H-mode, the mode in which ITER will operate. “Introduction to ITER,” Columbia University “The Physics of an Ignited Tokamak,” F. Troyon

9 Particle Confinement For ITER, τb = 400 s. a, minor radius (m) D, radial diffusion coefficient (m2/s) Burning plasmas refer to plasmas that are self-sustaining; that is, “In a burning fusion plasma so many fusion processes occur that the energy of the helium nuclei produced is almost or completely sufficient to maintain the temperature of the plasma.” (https://www.ipp.mpg.de/ /brplasma) Reaching the desired burn time is greatly influenced by the ability to confine alpha particles generated in the D-T fusion reaction. When alpha particles are confined for a sufficient amount of time, they are able to thermalize the plasma and support the burn time as needed. Generically, alpha particle confinement time can be approximated as the square of the minor radius divided by four times some diffusion coefficient. This ratio is required in ITER to ensure that thermal helium accumulation is less than 10% to avoid diluting fusion fuels. “ITER,” FusionWiki “Alpha Particle Confinement in Tokamaks,” R. B. White and H. E. Mynick “ITER Physics,” IAEA

10 H-Mode Confinement state“H-mode is an operating mode possible in toroidal magnetic confinement fusion devices. In this mode, the plasma is more stable and better confined.” (15.1) Ai, plasma ion mass (amu) n̄20, plasma line-average electron density B, toroidal magnetic field (T) R, major radius (m) a, minor radius (m) We previously mentioned that ITER’s most recent expression for energy confinement time is an H-mode correlation. So what is H-mode? The plasma edge refers to a region that extends from what is known as the “Last Closed Flux Surface” (LCFS) to a few centimeters inward. This region is critical in determining how well a confined plasma performs. When non-radiative power exceeds a given empirical threshold value as expressed by Eqn. 15.1, a two-fold energy confinement time for a confined plasma results and is associated with what is known as a barrier or edge pedestal. “High-confinement mode, Wikipedia” Fusion Plasma Physics, Dr. Weston M. Stacey

11 H-mode confinement stateSteep edge densities and temperature gradients are associated with the plasma edge. The H-mode has characteristic barrier or edge pedestals as illustrated in Figure 15.1. H-mode confinement was found to have been present in all tokamaks with auxiliary heating, and ITER will be no exception. However, the edge transport barrier is not yet fully understood despite 20 years of resesrch. Figure Edge pressure, temperature and density distributions in otherwise similar L-mode and H-mode discharges. (Data are plotted vs. a normalized poloidal flux function which is > 0 for values outside the LCFS and < 0 for values inside the LCFS. Location of the LCFS is indicated by the vertical dashed line) Fusion Plasma Physics, Dr. Weston M. Stacey

12 Instabilities – Microtearing Modes“Microtearing instabilities are magnetic field fluctuations that cause the formation of small island chains near rational magnetic surfaces.” These magnetic islands result when the radial pressure gradient is absent. Free Energy - The energy in a physical system that can be converted to do work. The correlation between free energy and confinement is such that when free energy decreases, confinement is lost. Instabilities often drive the loss of free energy. As such, instabilities can cause a loss of confinement. (http://www.uwyo.edu/physics/_files/docs/fusion%20-%20a%20viable%20energy%20source%20-%20questionable%20-%20sps%20seminar%20-% %203pm%20ps%20234.pdf) Previously, we discussed a few instabilities which included hydromagnetic, pinch, kink, flute, ballooning, and drift wave instabilities. Two other instabilities commonly associated with ITER include microtearing modes and edge localized modes (ELMS). Simulation of a m = 2, n = 1 magnetic island in an ignited ITER plasma. “Understanding and Predicting Microtearing Instabilities in the ST,” K. Tritz, et al. “ITER Physics Basis”

13 Instabilities – Microtearing ModesFigure The (m = 3, n = 1) magnetic island in a toroidal plasma Fusion Plasma Physics, Dr. Weston M. Stacey

14 Instabilities – Microtearing Modes“[M]icrotearing modes draw free energy from the background electron temperature gradient.” This is significant because “[i]n burning ITER plasmas, the fusion processes will predominantly heat the electrons.” Unstable microtearing modes have been found in the pedestal region of a simulated ITER plasma. These modes can generate radial electron thermal transport as great as Te ∼ 5 keV. “Gyrokinetic prediction of microtearing turbulence in standard tokamaks,” H. Doerk et al. “Microtearing instability in the ITER pedestal,” K. L. Wong et al.

15 Instabilities – Microtearing ModesIf magnetic islands associated with microtearing are allowed to grow large enough, they may limit plasma pressure thereby limiting both τE and degrading β— (6.110) n, density kB, Boltzmann Constant (J/K) T, Temperature (K) B, magnetic field (T) Μo, permeability of free space (m ∙ kg / A2 ∙ s2) As previously discussed in class, β can be considered a performance indictor for reactor efficiency; one would want to maximize plasma pressure and decrease magnetic field to both improve performance and decrease costs associated with with superconducting magnets. Or, β may be interpreted as how close the plasma is to reaching the Greenwald limit, a limit which when exceeded leads to disruption. Typically, we want β to be as large as possible, though usually, it is always significantly less that one, with most tokamaks having an associated β of about 0.01 or 1%. However, if the ratio of plasma pressure to magnetic pressure were to grow to large, instabilities and loss of confinement would result. The limit for β is known as the Troyon Limit. “ITER Physics Basis” Fusion Plasma Physics, Dr. Weston M. Stacey

16 Instabilities – Microtearing ModesTroyon Limit βN, normalized β I, current (MA) a, minor radius (m) B, toroidal magnetic field (T) βN was originally calculated by Francis Troyon to be 2.8, though some tokamaks have achieved values in excess of 3.5. As you can see from this image, ITER’s empirically calculated βN is about 1.4, with calculations for βN, max the to be However, this could be problematic, as βN a of 2.2 is required to reach ITER’s 1.5 GW fusion burn. This calculation suggests that ITER must operate at it’s maximum βN at the risk of instabilities and disruption in order to reach the required output. “Beta (plasma physics),” Wikipedia “Beta,” FusionWiki

17 INSTABILITIES – EDGE-LOCALIZED MODESEdge-localized modes (ELM) are instabilities that occur in the edge region of a tokamak plasma that result from periodic but irregular transport barrier relaxation. These instabilities are particularly damaging to the wall components of a tokamak, especially the divertor plates. “Edge-localized mode,” Wikipedia “Edge Localised Modes,” EUROfusion

18 INSTABILITIES – EDGE-LOCALIZED MODESITER computer models have demonstrated two mechanisms by which the flow of energy from the plasma comes into contact with the wall and divertor plates— Perturbed edge magnetic field energy loss Plasma filament expulsion Plasma filament losses are associated with small ELM losses, and that this energy is typically deposited over a large area. Plasma filament expulsion is analogous to solar flares. Despite ELMS being instabilities, they do prevent the plasma from becoming so dense that it exceeds its overall stability limit. If that were to happen, the plasma would undergo a major instability known as disruption, though two ELM-free operating modes with stable densities have previously been observed in other tokamak operations. “Edge-localized mode,” Wikipedia “Progress on ELM physics and ELM control,” ITER.org

19 INSTABILITIES – EDGE-LOCALIZED MODESELM Prevention and Control— Magnetic energy injection Pellet injection Outside of ELM-free modes, strategies to control these energetic bursts are being investigated. ELM amplitude could possibly be controlled by injecting static, magnetic, noisy energy into the containment field as a containment-stabilizing regime. Energy would use destructive interference to dampen the ELM. Pellet injection involves injecting frozen fuel pellets into the plasma to trigger ELM energy bursts so that they occur more frequently with decreased magnitude. Effects on plasma energy confinement have been minimal in recent experiments in other tokamaks, though in the past the toll of energy confinement has been greater. Researchers are investigating the use of pellet injection for ITER. “Edge-localized mode,” Wikipedia “Progress on ELM physics and ELM control,” ITER.org

20 Plasma-Facing Materials and componentsPlasma-facing materials are those materials that are used to construct plasma-facing components, such as the first wall and divertor plates. These components are subjected to high thermal flux, particle flux, and erosion. First wall materials must be carefully selected, as this surface may be a source of impurities which poison and cool the plasma. Plasma-facing materials are those materials that are used to construct plasma-facing components, such as the first wall and divertor plates. “Plasma Facing Components: Challenges for Nuclear Materials,” P. Magaud et al. Proceedings of the Third European Particle Accelerator Conference, Volume 1

21 Plasma-Facing Materials and componentsMaterials currently in use or under consideration for use multilayer, carbon-based tiles— Boron carbide Graphite Carbon fiber composite (CFC) Beryllium Tungsten Molybdenum Lithium Material currently in use or under consideration for use in tokamaks include boron carbide, graphite, CFC, beryllium, tungsten, molybdenum, and lithium. However, because ITER is so large and powerful as a tokamak, special considerations were made in developing the tiles used the line in the inside of the tokamak. Revisiting Figure 13.7 from our lectures, we’re reminded of why carbon is a good choice for plasma-facing materials. However, despite carbon’s tendencies not to poison a plasma, its is its tendency to retain tritium (and dueterium), which increases the risk of tritium releases in the event that there is a leak in the system. As such, beryllium was selected as the material for the first wall, and tungsten was selected for the divertor plates. Figure Energy dependence of the physical sputtering yield of deuterium- and self- sputtering surfaces of beryllium, carbon, and tungsten. “Plasma-facing material,” Wikipedia Fusion Plasma Physics, Dr. Weston M. Stacey “Overview of the JET Results with the ITER-Like Wall,” F. Romanelli

22 Plasma-Facing Materials and componentsIn 2009, a European JET was retrofitted with these tiles during a major shutdown, and the indicated that these tiles are likely to work well in ITER, as plasma impurities were much reduced when compared to the JET it’s original configuration. Additionally, the amount of fuel being retained in the walls of the JET with the ITER-like walls was greatly reduced by a factor of ten, and the wall was found to be significantly more resistant to erosion. “New JET results tick all the boxes for ITER,” EUROfusion

23 MAGNET SYSTEM Toroidal Field System Poloidal Field SystemUnsurprisingly, ITER’s magnet system will be the largest superconducting magnet system in the world with a combined stored magnetic energy of 51 Gigajoules (GJ). Toroidal Field System – 18 D-shaped toroidal field magnets whose primary unction is plasma confinement. This system can produce 41 gigajoules of magnetic energy with a maximum field of 11.8 T. Poloidal Field System – 6 ring-shaped poloidal field magnets shape the plasma and contribute to stability by pinching it away from the walls. This system can produce 4 gigajoules of magnetic energy with a maximum field of 6 T. Toroidal Field System Poloidal Field System “Magnets,” ITER.org

24 MAGNET SYSTEM Central Solenoid In-Vessel Coils “Magnets,” ITER.orgCentral Solenoid – Responsible for inducing strong current into the plasma with a stored magnetic energy of 6.4 gigajoules. The central solenoid can induce 15 megaamperes for seconds. It’s maximum magnetic field is 13 T. In-Vessel Coils – This non-superconducting coil system can create resonant magnetic perturbations in the plamsa to defeat instabilities associated with Edge-Localized Modes. Central Solenoid In-Vessel Coils “Magnets,” ITER.org

25 Confinement time dependency Geometry effects on enhanced confinement Will ITER Work? Examine previous performance objectives of similar tokamaks to determine operational parameters: Confinement time dependency Geometry effects on enhanced confinement Moderating Instabilities Determining whether or not ITER will work is a difficult task seeing that we have to extrapolate from previous studies conducted on quasi-replica tokamaks that can only provide indications of how ITER will work. In order to understand the validity of this approach we will examine previous discoveries from tokamaks such a the Joint European Torus (JET), Japan Torus 60, DIII-D and a few smaller magnetic confinement tokamaks. These tokamaks form the basic database that ITER uses to generate the empirical data points for its projected confinement time and geometry. We will look at the parameters that Desiree outlined in her theory portion and provide examples of real world applications. “Scaling laws,” DOE

26 Geometry of plasma and field linesPhysics vs Empirical Data Grad-Shafranov Equation: Defines axis symmetry equilibrium found in a tokamak Equilibrium parameters determined through field line and flux surface topology (6.33) Physics of plasma shaping limited to predict certain instabilities Ampere’s law and the force balance equations give rise to the Grad-Shafranov Equation: Showing equilibrium for tokamak symmetry. Using this equations helps model closed fluxed surfaces as a function of magnetic pressures, field line contours, and current profiles. The topology of the plasma governed by the field lines provides physics based confinement of the plasma in a reduce two dimensionally analysis of the Tokamak geometry. As the MHD theory is well defined in the modeling and testing of plasma physics for Tokamaks, the instabilities generated from gradients in current profiles, temperature distributions and density fluctuations are not and have deterministic effects, meaning that physics projections due not tell the full story of the plasma (as of yet). Empirical data points are used to create correlations and trends that help provide corrections based on the observed phenomena. Fusion Plasma Physics, Dr. Weston M. Stacey

27 ASDEX Confinement discovery1982 – High confinement discovery Correlation to plasma geometry and temperature Increased confinement time by three folds ~ 1.8s The ASDEX tokamak showed that high temperatures and geometry of field lines/separatrix created a “high” H confinement region for tokamaks governed by the edge localize modes of the plasma. Auxiliary heating (either from ohmically heating , RF waves, Neutral Beam or pellet injection heating) – in this case NBI created a enhanced density and temperature gradients at the edge of plasma that led to a transport barrier confining particle flux and increasing confinement time. The Single Null Diverter configuration used by the Germans in the early 80’s led to in-depth research to H-mode confinement conditions and instabilities at the plasma edge. “During 50 years of fusion Resarch,” Dale Mead, IAEA.

28 Limits on Heating the plasma –Alcator-c modeAlacator-C mode Produced desire plasma heating without superconductive magnets through auxiliary ICRH source ITER will mirror this approach with the addition of improved ohmic heating and neutral beam injection The initial limitations of heating the plasma in early research was not bond by the physics of the configuration but instead the advancements of technology at the time (i.e. superconductors). The inductance provided for the plasma current is generating in the central solenoid. This current augmented by the bootstrap current effect of trapped particle-orbits transfer momentum and energy across the plasma species creating the extreme heat needed for the H –mode to take effect. The Alacator Cmode test at MIT achieved the highest magnetic field approaching 8Tesla without the use of superconductors. Without the Central Solenoid current drive heating, the reactor used Ion Cyclotron heating at 80MHz to achieve the desire heating range of 3 keV for the electrons producing improve confinement time (still fractions of a second). In order for ITER to initial reach temperatures in the range of 150 million degrees center, it will make use of the superconductive magnets outline earlier for improved ohmic heating, high frequency radio waves and neutral beam injection all of which will share its kinetic energy through collisional transfer increasing the core temperature. “An Alcator Chronicle,” Ron Parker

29 Neoclassical confinement time does not align with observations JEt Neoclassical confinement time does not align with observations Confinement time linear coupled to current and inversely power production. Illustrated anomalous transport not governed by physics projection Goldston’s scaling first introduced Understanding that heat created through current plays a key role in confinement, we will look at the Joint European Torus indications for confinement. Neoclassical confinement times shows an inverse relationship to plasma density which is proven to be the opposite as higher densities align with improved confinement times. The neoclassical approach also align increased confinement times linear to that of heating power. Jet showed for three separate current profile as a function of power, the confinement time degraded at higher heating powers while higher currents improved confinement. Goldston scaling was first introduced deviating from physics derivations to empirical observations. Side note, UK pulling out of the EU has taken a considerable toll on JETs future as it is currently only funded through 2018 and will have renegotiate the contracts involved with the member states. This is important as JET is the only Deuterium – Tritium fueled tokamak representative of how ITER will operate with first wall material. The delays inherent with JET will no doubtedly lead to more delays with ITER. “The science of JET,” John Wesson.

30 Goldston’s scaling requires 30MA! Jet (cont) Goldston’s scaling requires 30MA! Reshaping the plasma and magnetic field creates desired separatrix H mode achieved with 60% improvement in confinement at same power levels Using Goldston’s scaling law and extrapolating for current to reach the desired confinement times, it would take nearly 30 MA of current to meet the heating requirements for confinement. While possible, it would be prohibitedly expensive and detract from the overarching goal of net power production (Q > 10). Fortunately, the German discovery of the H mode confinement gave way for JET not only to exploit heating the plasma but also shaping it to achieve desired confinement times. Creating the x-point indicative of a separatrix layer in the field alignment provided a transition form low to high confinement with nearly 60% increased in desired edge temperatures and confinement times. “The science of JET,” John Wesson.

31 Premier plasma shaping tokamak DIII-D Premier plasma shaping tokamak Modeled confinement time in excess of 300s Internal Transport Barrier optimization Enter DIII-D the flagship tokamak for examining plasma shaping and the effects on phenomena such as bootstrap current drive, confinement time improvement and reduction in edge localized mode instabilities. DIII-D plays a pivotal role in determining optimized plasma and magnetic field line shapes to reach goals such as the burning plasma scenario outlined earlier. Key goals for DIII-D is to help model scenarios at high Normalized Beta values with safety factors operating at q=3.5 and to operate at steady state where external heating is reduced to near zero values as alpha heating and bootstrap current drive is optimized for steady state operations. “DIII-D Development Plan,” General Atomics R.D. Stambaugh

32 Highest triple point achieved in a tokamak JT 60 Highest triple point achieved in a tokamak Operates D-D fuel reactions (currently under upgrades for supporting Tritium fuel) High inductive heating from auxiliary sources The closes tokamak to achieving actually steady state operation with moderate Beta limits is the JT 60 tokamak but under very specialized conditions. 1) It achieve the highest triple point to date at 1.77 x 10^28 K S M by using D-D fuel reactions which in itself limits how far one could extrapolate to ITER operating parameters. And 2) It operated under full inductive current drive through the use of its superconductors creating a 5.5MA current to achieve the temperature, density and confinement time in the triple point. Where as ITER will work to produce similar results with less inductive power and proportional normalized beta values. “JT-60 Plasma Regime” Y. Kamada, JAEA.

33 Goldston’s scaling ASDEX, JET, DIII-D and JT-60 and others all demonstrate the key components that derived the current scaling law Its important to see how these discoveries played a key role in the current confinement time scaling laws first put forth by Goldston. Neglecting inherent properties of Ions used in the equiation, the current empirical driving confinement time is directly proportional to the shaping characteristics of the plasma and the heating sources. Though deviations to this scaling law are prevalent in every tokamak, it is one of a few scaling proportionality constants that help show a trend projected to the parameters of ITER. Heating Plasma Shaping Plasma Fusion Plasma Physics, Dr. Weston M. Stacey

34 Confinement time shortfallQ < 1! These scaling laws do not come without limitations. Though we see a steady growth in plasma temperature, densities and confinement times critical for the triple point performance criteria, no tokamak reactor has yet produced a net gain. Confinements times greater than needed by ITER have been achieved, as well as core temperatures but no one has been able to achieve all the parameters needed to reach break even and ignition. ITER conceptual meets the requirements of the scaling factor thorugh its larger size plasma and higher H mode confinement models but it is still a model projection with unanswered deviations. Namely, how does instabilities play a role in future tokamaks. Progress in MFE Science- Tokamak Research, R.D. Stombaugh

35 Instabilities Effects of impuritiesMain source: Helium Ash – kinetic energy depleted First Wall Sputtering Interaction between plasma edge And material surface Instabilities drive free energy from fusion reaction and produced localized or global gradients leading to failure. Balloning, kink and tearing modes with MHD instabilities are limiting factors for the physical size parameters of a tokamak against its beta and density limit as well as safety factor for confinement. In addition as desiree noted, impurities in the plasma will divert free energy away from fusion and dilute the fuel cooling and leading to failure. Two sources of impurities are 1) helium ash which refers to the alpha particles that have transferred all the energy and reside in the D-T fuel in thermo-equilibrium. And 2) impurities stripped from the first wall from sputtering and shear conduction melting lead to gradient temperature and densities in the plasma that drive further instabilities. “The Challenge of Plasma Surface Interaction,” Dennis Whyte MIT

36 Effects of impurities (CONT)Impurities can degrade plasma performance with as little as 10 mm3 of material Diverting material away from core key to sustained confinement ITER will implement additional control mechanism to moderate impurities and MHD instabilities MIT conducted a study of impurities effects from plasma facing materials such as limiters plates and first wall material and noted that as little as 10 mm^3 of material could create localized instability within the plasma and cause failure. Initial limiter plates composed of molybdenum exposed to the heat of the plasma melted in microseconds. Without the precise configuration of the separatrix at the Scrap off Layer caring impurities down to the diverter, impurities would lead to tokamak instabilities and failure. In order for ITER to overcome these MHD instabilities, microtearing and impuritites, it will employ untested technology such as a corrections coils (introducing a forth external magnetic field) that will help in theory shape plasma and reduce gradients in temperature, density and current profiles thereby reducing instabilities and diverting impurities. “Magnetic confinement fusion,” Wikipedia

37 Other Confinement devicesIt is important to note that there are parallel research taken place outside of the tokamak design. One key competitor to the magnetically confined tokmak is the inertial confinement. Common approaches used today are an array of lasers point at a singular fuel source and rapidly concentrate energy needed to create the temperatures of fusion. Though beyond the scope of this report, some conflicting reports from the national ignition facility claim they will reach ignition before ITER is turned on. Overview of Fusion Research in Japan, Masayohi Sugitmo

38 Will it iter work? YES* * ITER work for its intended purpose. To provide more degree of freedom modeling a testing with higher heating sources, magnetic confinement times. For ITER to achieve more ambitoue goals of ignition and net production Q > 10 will no doubt be a iterative process as new instabilities and analmalous transport is boudn to arise. ITER work for its intended purpose. To provide more degrees of freedom modeling and testing with a stronger heating source, magnetic inductance from higher currents and ability to parametrically change the plasma magnetic field line gemotry. ITER will provide empirical data points for tools like COMSOL and other Multiphysics languages to model higher degrees of freedoms with high accuracy. ITER is not DEMO (a commercial prototype) but instead another research tool on a very long journey to fusion power. For ITER to achieve more ambitious goals of ignition and net production Q > 10 will no doubt be a iterative process as new instabilities and anomalous transport is bound to arise but will be able to exploit its powerful flexibility to help determine the route causes of this phenomena thereby creating a foothold

39 Will ITER Work? Philosophical approachKardashev Scale: “measuring” the advancement of society Extrapolates based on energy production Basis of several NASA missions Fusion alone is the only sourced deemed capable of launching us towards the next level of Advancement… The Kardashev scale was proposed by a Russian astrophysicist that cited a hypothetical way to measure extra-terressiteal societies if ever found. Though hypothetical, the scaling law was a key component of NASA research as they sent unmanned missions to distant realms of the solar system and beyond looking for signals of higher level of energy consumption from nearby stars. Kardashev scale is also a colloquial scale used by modern day physicist to project when we as a species will move to the next level of advancement. Following popular trends from companies like virgin galactic, space X, the planetary space foundation and private power developers such general atomics, the most notable block towards our advancement is providing a energy source that will meet the exponential growth of the future. As such, leading minds in the field such michiu kaku and William deshazer have noted only one source dense enough to meet the challenge, Fusion. ITER will work because of the immense the share collective intelligence community devoted to achieving the next step in securing our future, unlimited energy. “Kardashev Scale,” Wikipedia

40 questions

41 “When we look up at night and view the stars, everything we see is shinning because of distant nuclear fusion.” -Carl Sagan