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Cover-Relevance of Advanced Nuclear Fusion Research "Relevance of Advanced Nuclear Fusion Research: Breakthroughs and Obstructions" Bruno Coppi Massachusetts Institute of Technology Norman Rostoker Memorial Symposium University of California, Irvine, 24-25 August 2015 1 Fusion Reactions to be Exploited (with existing technologies in order to produce basic knowledge of high energy plasmas and to attempt realizing a net energy generation system) D-T D-D D-3He p-11B 2 Advancements in nuclear fusion research are rated in terms of criteria (but not all) to be met in order to achieve DT ignition conditions. D + T → 4 He + n simplified ignition condition Te ! Ti nD + nT = ne 3.5 MeV εα ! 4 Example of Illusions (emerged at the time of the AEC to ERDA to DOE Transitions) • To produce an energy generating system skipping the basic plasma physics research that a good scientific tradition would suggest • To underestimate the consequences of not valuing an adequate understanding of high energy plasmas and the benefits of advanced technology developments (e.g. high magnetic fields) spurred by fusion research 3 Scalings 2 σ v F ∝Ti in the range of temperature of interest nTτ E ≡ PM (parameter of merit) 8 n T T 2 π ⎣⎡ ( e + i )⎦⎤ nTe ! β p Bpc1 β p = 2 Bp α1 α2 τ e ! n B I pc2 A combination of high poloidal fields (Bp) and total plasma current (Ip) is the indicated prescription. Note that the reactivity scales as 5 On the other hand besides avoiding these illusions, a relatively wide spectrum of approaches and, consequently of constructed and operated machines, should be developed (rather than suppressed). For instance i) the high density, high field approach to get near ignition conditions, (e.g. Ignitor) ii) plasma confinement configurations sustained by the injection of high energy particle populations etc. (e.g. Trialpha, U.S., G.D.T., Russia) iii) steady state confinement experiments (e.g. Tokamak Energy, U.K.) 6 Additional Remarks • Purity Requirements • Attaining the ideal ignition conditions as an intermediate but necessary goal • Fusion with Polarized Nuclei Model for Pulsars (Bright Spot) (corresponding to a local dip in the transverse thermal conductivity) B ! Bez 2 2 0 1 ⎛ ∂ D⊥ ⎞ 2 ∂D⊥ ⎞ ∂ D⊥ ⎞ D⊥ ! D⊥ + 2 (ℓ − ℓ 0 ) ; ⎟ = 0; 2 > 0 2 ⎜ ∂ ⎟ ∂ ⎠ ∂ ⎟ ⎝ ℓ ⎠ ℓ l=l0 ℓ ⎠ l=l 0 Oversimplified Thermal Energy Balance Equations " Te ! Te (ℓ − ℓ 0 , x = x0 )exp ⎡γ t + ik⊥ (x − x0 )⎤ ⎣ ⎦ Model for Pulsars (corresponding to a local dip in the longitudinal thermal conductivity) B ! Bez 2 0 1 ∂ D! 2 D! " D! + 2 (x − x0 ) 2 ∂x Oversimplified Thermal Energy Balance Equations ˆ dS ˆ dS S = Ti where > 0 dTi dTi Figure 1. Vertical cross section of the Ignitor machine as presently designed External Electromagnetic Poloidal Coil radial press (n° 9-14) (n° 15, 16) Bracing ring Plasma Chamber Toroidal Field Coil Central Solenoid (n°1-8) Figure 2. Sketch of the vertical cross section of the Ignitor machine where the main components are indicated. 12 External Electromagnetic Poloidal Coil radial press (n° 9-14) (n° 15, 16) Bracing ring Plasma Chamber Toroidal Field Coil Central Solenoid (n°1-8) FIG. 1. Vertical cross section of the Ignitor FIG. 2. Sketch of the vertical cross section of the Ignitor machine as presently designed. machine where the main components are indicated. FIG. 3. “Bucking and Wedging”solution. The objective is to minimize the unbalance between the principal stress components. 17 FIG. 5. Plasma chamber with access ports. FIG. 4. View from above the core of the Ignitor machine. The subdivision of it into 12 modules is evident. TABLE I: EXAMPLE OF PLASMA PARAMETERS [1] FOR AN 11MA OPERATIONAL SCENARIO (JETTO CODE). ! 11th European Conference on Applied Superconductivity (EUCAS2013) IOP Publishing Journal of Physics: Conference Series 507 (2014) 032030 doi:10.1088/1742-6596/507/3/032030 The forces in the outer joint are supported by bolts. A steel tension ring supports the upper leg on the top joint. The forces in the central column are supported by wedging of the TF coils against each other, and by buckling against the central solenoid. The central solenoid is filled with a fiberglass/epoxy plug to reduce the maximum stresses in this region. Figure 1. Schematic design of the TF coil system. (Left) assembled; (right) disassembled. The structure is made of stainless steel 316LN, the cables are YBCO conductors. The central solenoid is filled with a fibreglass/epoxy plug to take the compressive loads on the inside. A finite element method (FEM) simulation of the Lorentz loads in the TF coils was made to estimate the stresses in the structure. The model is half a single TF coil. The load in the coils is due to the Lorentz force in the conductors due to the toroidal magnetic field generated by all 18 coils. Roller boundaries simulate the rotational symmetry, and the contact between the two legs. The simulation results are shown in figure 2. The maximum stress in the structure is approximately 700 MPa and the yield strength of stainless steel 316LN is larger than 1000 MPa [2], which gives a safety factor of approximately 1.4. 1 GPa 0.5 GPa 0 GPa Figure 2. Results of FEM simulation of the stresses in the TF coils. (Left) bottom leg; (right) top leg. The colors represent the von Mises stress. The safety factor is approximately 1.4 in the worst areas. To provide the 9.2 T on axis, a current of 8.4 MA turn is required in each TF coil. The current is carried by 70 kA YBCO cables; each cable composed by 250 YBCO tapes (25 mm width) assembled using the Twisted Stacked Tape Conductor method [3]. The superconductors are cooled with liquid 2 11th European Conference on Applied Superconductivity (EUCAS2013) IOP Publishing Journal of Physics: Conference Series 507 (2014) 032030 doi:10.1088/1742-6596/507/3/032030 Demountable Toroidal Field Magnets for Use in a Compact Modular Fusion Reactor F. J. Mangiarotti*, J. Goh, M. Takayasu, L. Bromberg, J. V. Minervini and D. Whyte Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, MA 02139, USA *E-mail: [email protected] Abstract. A concept of demountable toroidal field magnets for a compact fusion reactor is discussed. The magnets generate a magnetic field of 9.2 T on axis, in a 3.3 m major radius tokamak. Subcooled YBCO conductors have a critical current density adequate to provide this large magnetic field, while operating at 20 K reduces thermodynamic cooling cost of the resistive electrical joints. Demountable magnets allow for vertical replacement and maintenance of internal components, potentially reducing cost and time of maintenance when compared to traditional sector maintenance. Preliminary measurements of contact resistance of a demountable YBCO electrical joint between are presented. 1. Introduction The recent development of YBCO superconducting tapes and cabling methods could be a revolutionary development for magnetic fusion. Subcooled YBCO has larger critical current density at high magnetic fields (more than 20 T) than low temperature superconductors (LTS) such as Nb3Sn and NbTi. Also, YBCO can be operated at higher temperatures than LTS, reducing the thermodynamic cooling cost and allowing resistive loss in the coil joints. An innovative concept of fusion reactor has been developed in 2012 by the MIT Fusion Reactor Design course, partially inspired by the Vulcan concept design [1]. A comprehensive report of the characteristics of the reactor is expected to be published later this year. The reactor is 3.3 m in major radius and operates in steady state. The magnetic field on axis is 9.2 T. The tritium breeding blanket is entirely made of liquid FLiBe, and the toroidal field (TF) coils are demountable, allowing for vertical replacement of the internal components of the reactor. This maintenance scheme is much faster, easier and cheaper than sector maintenance, and the replaceable parts such as the vacuum vessel can be fabricated off-site with lower tolerances. We developed a concept of demountable toroidal field coils for a fusion reactor, with preliminary stress and heating simulations. We have designed demountable electrical joints for YBCO stacked tape conductors for the TF coil system, and tested a small scale prototype of the electrical joint. 2. Toroidal field magnets concept and stress analysis The TF coil system is composed by 18 demountable coils. The shape of the coils is based on the constant tension D-shape. The coil is divided in two parts, as shown in figure 1: a removable upper leg and a stationary lower leg. The legs are joined in the outer midplane, and in the top of the coils. The structure of the coils is made of stainless steel 316LN. Content from this work may be used under the terms of the Creative Commons Attribution 3.0 licence. Any further distribution of this work must maintain attribution to the author(s) and the title of the work, journal citation and DOI. Published under licence by IOP Publishing Ltd 1 From: "Bruno Coppi" <[email protected]> Subject: [Fwd: fusion in the local paper in France] Date: Wed, August 19, 2015 3:06 pm To: ---------------------------- Original Message ---------------------------- Subject: fusion in the local paper in France From: "Lawrence R. Sulak" <[email protected]> Date: Sun, August 16, 2015 6:26 am To: "Bruno Coppi" <[email protected]> -------------------------------------------------------------------------- Dear Bruno, Have not talked with you for way way too long! I'm again at CERN for the summer... We need time together for me to get caught up. Just read a blurb in La Provence Friday re: an MIT proposal by Dennis Whyte to use HiTc magnets. Anything to it? The article also says that Lockheed-Martin is pursuing fusion.
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