The Heavy Ion Fusion Virtual National Laboratory SIMULATIONS OF TARGETS FOR NDCX II* J. J. Barnard 1, J. Armijo 2, F. M. Bieniosek 2, A. Friedman 1, M.

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Presentation transcript:

The Heavy Ion Fusion Virtual National Laboratory SIMULATIONS OF TARGETS FOR NDCX II* J. J. Barnard 1, J. Armijo 2, F. M. Bieniosek 2, A. Friedman 1, M. Hay 2, E. Henestroza 2, B.G. Logan 2, R. M. More 2, P. A. Ni 2, L. J. Perkins 1, S. F. Ng 2,4, S. A. Veitzer 3, J. S. Wurtele 2, S. S. Yu 2,4, A. B. Zylstra 2 1. Lawrence Livermore National Laboratory, Livermore, CA 94550, USA 2. Lawrence Berkeley, National Laboratory, Berkeley, CA USA 3. Tech-X Corporation, Boulder, CO USA 4. Chinese University, Hong Kong, China Twelfth US-Japan Workshop on Heavy Ion Fusion and High Energy Density Physics San Francisco, CA September 6 – 11, 2009 *Work performed under the auspices of the U.S. Department of Energy under contract DE-AC52-07NA27344 at LLNL, and University of California contract DE-AC02-05CH11231 at LBNL

The Heavy Ion Fusion Virtual National Laboratory NDCX II will serve as a platform for warm dense matter experiments and as a test bed for heavy ion fusion 1. Experimental concepts for Warm Dense Matter (WDM) a.planar solid targets b.metallic foams c. cylindrical "bubbles" d. spherical bubbles 2. Connecting simulations of WDM targets to diagnostics a. simulating brightness temperature at critical density point b. simulating velocity at critical density point 3. Simulations of experiments relevant to Heavy Ion Fusion (HIF) a. coupling physics: two-pulse/ ramped pulse experiments

The Heavy Ion Fusion Virtual National Laboratory Complementary oral talks at IFSA cover other aspects of NDCX I and NDCX II Oral Alex Friedman, Wednesday, 9/9, 3:20 pm PHYSICS DESIGN FOR NDCX-II, A SHORT-PULSE ION BEAM DRIVER FOR NEAR-TERM WDM AND TARGET PHYSICS STUDIES Oral Frank Bieniosek, Wednesday, 9/9, 3:00 pm ION-BEAM-DRIVEN WARM DENSE MATTER EXPERIMENTS

The Heavy Ion Fusion Virtual National Laboratory NDCX II MeV, 0.03  C Completion date: 2011 NDCX I 0.35 MeV,  C Now NDCX I is laying the groundwork for NDCX II Bragg peak (uniform) heating T ~1-2 eV in planar metal targets (higher in cylindrical/spherical implosions) Ion + /Ion - plasmas Critical point; complete liquid/ vapor boundary Transport physics (e-cond. etc) HIF coupling and beam physics Explore metal liquid/vapor boundaries at T ~ 0.4 eV Evaporation rates/ bubble and droplet formation Test beam compression physics Test diagnostics

The Heavy Ion Fusion Virtual National Laboratory Several target options have been considered for WDM studies on NDCX II Solid planar targets 3.5  1 mm spot diameter Cylindrical "bubble" targets Ion beam 1 mm spot diameter 3.5  >6  hole diameter Spherical bubble targets Ion beam 1 mm spot diameter 3.5  1  bubble diameter Foam planar targets Ion beam 1 mm spot diameter 35   for 10% foam  Foam densities ~ few % to solid Pore size ~ nm to ~  m Ion beam Expected regime: ~1.2 eV, 0.2 Mbar

The Heavy Ion Fusion Virtual National Laboratory The nominal beam assumes a 30 J/cm MeV Li ion beam, corresponding to 20 kJ/g in Al (SRIM) SRIM HYDRA/ QEOS For HYDRA 1 runs we assume the nominal beam results in 20 kJ/g in Al. This implies the simulated beam had a fluence of 20 J/cm 2 (instead of 30 J/cm 2 ) Solid planar targets 3.5  1 mm spot diameter Ion beam Expected regime: ~1.2 eV, 0.2 Mbar 1. M. M. Marinak, G. D. Kerbel, N. A. Gentile, O. Jones, D. Munro, S. Pollaine, T. R. Dittrich, and S. W. Haan, Phys. Plasmas 8, 2275 (2001).

An example of two significantly different EOS QEOS LEOS Critical point: p=0.029 MBar  =0.78 g/cm 3 T=0.945 eV p= MBar  =0.70 g/cm 3 T=0.633 eV + + Log[  (g/cm 3 )] Log[ T  (keV)] Aluminum Critical point:

The Heavy Ion Fusion Virtual National Laboratory Evolution of center of 3.5  thick Al foil over the heating phase (1 ns) using QEOS without maxwell construction density temperature pressure Z*

Evolution of center of 3.5  thick Al foil over the heating phase (1 ns) using QEOS without maxwell construction LEOS CP QEOS CP vzvz entropy T 

The Heavy Ion Fusion Virtual National Laboratory Target evolution was tracked for 30 ns Temperature vzvz T  Entropy

Critical frequency crit defines "over dense" point where wave propagation becomes evanescent Consider idealized case: Energy instantaneously deposited; ideal gas; Z* = constant z/L c s t/L z/L c s t/L For adiabatic evolution lines of constant density coincide with lines of constant temperature (since T ~   -1 ). density Density contours

The Heavy Ion Fusion Virtual National Laboratory As estimate of brightness temperature T b at a given  we may take the black body intensity at the temperature of the critical point TbTb c s t/L z/L - Brightness temperature will stay constant until contour reaches z axis - Brightness temperature will stay constant for longer times at lower frequencies Density contours

The Heavy Ion Fusion Virtual National Laboratory For the actual target case (QEOS shown here) we may plot h crit vs z and T(h crit ) vs t for several h crit 's Model assumes: T b = T(h crit ) if h critmin < h < h critmax T b = Tmax if h > h critmax T b = 0 if h < h critmin T max 150 nm (8.3 eV) (UV) 450 nm (2.4 eV) (Green visible) 1500 nm (0.83 eV) (IR) h crit z (microns)

The Heavy Ion Fusion Virtual National Laboratory We may compare the same plots for different intensities Upper set: 20 kJ/gm Middle set: 15 kJ/gm Lower set: 10 kJ/g (Magenta curves: T max ; Blue curves: 150 nm Green curves: 450 nm; Red curves: 1500 nm) (UV most sensitive to change in deposited energy; IR (which samples cooler part of blowoff, less sensitive)

The Heavy Ion Fusion Virtual National Laboratory We may also compare two equations of state Upper set: LEOS without Maxwell construction Lower set: QEOS without Maxwell construction Now IR is most sensitive to the EOS, and the two EOS should be distinguishable (Magenta curves: T max ; Blue curves: 150 nm Green curves: 450 nm; Red curves: 1500 nm)

The Heavy Ion Fusion Virtual National Laboratory We may also compare the same equation of state with or without the Maxwell construction Upper set: LEOS with Maxwell construction Lower set: LEOS without Maxwell construction (Magenta: T max ; Blue: 150 nm Green: 450 nm; Red: 1500 nm) Now IR is VERY sensitive to the choice of Maxwell construction or no Maxwell construction

The Heavy Ion Fusion Virtual National Laboratory We may also calculate the velocity at the critical density for a particular photon frequency as a function of time Again looking at the idealized case (instantaneous heating, ideal gas, constant Z*): Density contours Velocity contours T critical_dens c s t/L Time at which density contour reaches z=0 axis c s t/L v critical_dens /c s The velocity contours first align with, then cross the density and temperature contours, so the velocity measured at the critical density would first be constant then plummet z/L c s t/L

The Heavy Ion Fusion Virtual National Laboratory For realistic equations of state and finite heating time the velocity would also reach zero at the end of the flattop in T b (Magenta: Velocity of outermost zone; Blue: 150 nm Green: 450 nm; Red: 1500 nm) Upper set: LEOS with Maxwell construction Lower set: QEOS without Maxwell construction Again, the IR is best suited for distinguishing different EOS

The Heavy Ion Fusion Virtual National Laboratory A cylindrical hole can create regions of temperature and pressure larger than in a simple foil 44 66 T T T TT T eV eV eV eV eV HYDRA simulations by E. Henestroza (using LEOS). Solid Tin target. 2.8 MeV Li +, 10 J/cm 2 assumed. T max = 2.6 eV; P max = 1.3 Mbar  max = 11 g/cm 3 (  init = 7 g/cm 3 ); v imp = 3.5 km/s Advantage: relatively easy to manufacture and diagnose Ion beam

If instead of a cylindrical hole, a spherical void is placed in the foil, higher pressures are possible Ion beam 3.5  1  bubble diameter Simulations by Siu-Fai Ng (using DISHr, QEOS) P max > 10 Mbar, T max > 10 eV,  max > 5 g/cm 3 t (ns) t (ns) t (ns) Central Pressure (bar) 10M Central Temp (eV) 10 Central density (gcm -3 ) radius (  m) 0.5 t (ns) Simulation: 1.75  0.5  Deposition: 25 kJ/g/ns for 1 ns

The Heavy Ion Fusion Virtual National Laboratory Foams have been modeled as layers of solid separated by layers of void 15 layers Evaporate Homogenize Expansion/ release Codes used on foam modeling include: DPC (Saha based EOS), HYDRA (using QEOS), and DISH (using van der Waals EOS) Foams of interest because: 1.Intrinsic physics 2.Radiator for HIF 3.Structural material in ICF

The Heavy Ion Fusion Virtual National Laboratory NDCX II will also study ion beam coupling physics that is key to creating high gain direct drive targets for Inertial Fusion Energy Fuel Ablator Initial ion range Fuel Unique features of heavy ion direct drive can maximize drive efficiency: 1. Passive approach: Ion beam heating causes electron thermal speed to go above ion velocity ==> range lengthens, and ion beam can stay close to ablation front, (if ion energy is sufficiently low) 2. Active approach: Ramping ion beam energy over the course of the pulse, will also increase range. Ion beam Ablation front Ion beam initially heats ablator Later in time: Blow-off plasma v ~ c s Ablation front would separate from location where energy is deposited ==> Potential low coupling efficiency Direct drive capsule

Recent heavy ion capsule designs by Perkins show NIF target yields at 1/4 to 1/3 the driver energy of NIF (from J. Perkins et al, Hirschegg Presentation, 2009).

The Heavy Ion Fusion Virtual National Laboratory Conclusions NDCX II is being designed for both Warm Dense Matter (WDM) and Heavy Ion Fusion (HIF) applications For WDM, several target geometries lead to warm dense matter conditions - planar targets at ~ 1 eV,.5 MBar are predicted; - cylindrical imploding bubbles will reach a few eV, 1 MBar - spherical imploding bubbles can reach ~10 eV, 10 Mbar Foam dynamics are of interest for both WDM and HIF applications. NDCX II pyrometry experiments should relatively easily be able to distinguish between specific equations of state (for example, QEOS and LEOS). VISAR experiments may also be able to distinguish different EOS. For HIF, we are exploring direct drive concepts that have high coupling efficiency, by utilizing temperature dependent range and ramped ion energy. NDCX II will be able to test key aspect of direct drive target concept: changing ion energy to keep ion deposition point close to ablation front. Beam physics such as wobbler, and beaming bending can be tested.

The Heavy Ion Fusion Virtual National Laboratory

Typical data in foil targets shows heating from the prepulse and compressed pulse on NDCX I Streak-spectrometer data in Au target showing transition from continuum emission to emission lines from heated gold

The Heavy Ion Fusion Virtual National Laboratory Abstract The Neutralized Drift Compression Experiment II (NDCX II) is an induction accelerator now planned for completion in The baseline design calls for a 3 MeV, 30 A Li + ion beam, delivered in a bunch with characteristic pulse duration of 1 ns, and transverse dimension of order 1 mm. The purpose of NDCX II is to carry out experimental studies of material in the warm dense matter regime, and ion beam/hydrodynamic coupling experiments relevant to heavy ion based inertial fusion energy. In preparation for this new machine, we have carried out hydrodynamic simulations of ion-beam-heated, metallic targets, connecting observable quantities with the simulated density, temperature, and velocity. Simulated target geometries include spherical and cylindrical bubbles (to create enhanced regions of higher pressure and temperature), in addition to planar solid and planar foam targets. Pulse formats include single pulses of fixed ion energy, and double pulses with varied energy (or single pulses with ion energy that changes over the pulse) to investigate ion coupling efficiency, motivated by simulations of ion driven direct drive capsules that have shown high coupling efficiencies at low total pulse energy (< 1 MJ).

The Heavy Ion Fusion Virtual National Laboratory From presentation by Dmitry Nikolaev July 6, 2009, LBNL

The Heavy Ion Fusion Virtual National Laboratory Is NDCX II near an optimum in tradeoff between pulse energy vs. pulse duration? One figure of merit is central pressure in the foil, since it reflects both high density and high temperature 20 kJ/g (30 J/cm 2 ) 10 kJ/g (15 J/cm 2 )Design point Maximum central pressure Example: If the pulse duration is reduced to 0.62 ns and the pulse energy reduced to 10 kJ/g, the same central pressure is reached.

The Heavy Ion Fusion Virtual National Laboratory Outline We present HYDRA simulations of solid foil targets using a beam with NDCX II parameters Questions addressed: 1. Can we reach the critical point in metals such as Al with NDCX II? 2. Can we use pyrometry or VISAR measurements to distinguish between equations of state? 3. Are we at the optimum combination of pulse duration and total pulse energy?

The Heavy Ion Fusion Virtual National Laboratory Heavy-ion direct drive LASNEX runs by John Perkins found gains ≥ 50 at 1MJ with high coupling efficiency (15%). HI beam power ~14 Time (ns) ~250T W 1.0MJ 0 3  m solid CH shell DT gas DT fuel 1.9mm Ablator 2.00mm Heavy-ion direct drive (1MJ) 50 MeV Argon Higher efficiencies and gains may be possible by using energy ramp Coupling efficiency Target gain (at 1MJ drive) Laser Indirect Drive ~ 2-4% ~ 10 Laser Direct Drive ~ 5-8% ~ 25 Heavy ion direct drive with energy ramp ~ 25% ~ 100 Ablator rho-R (g cm-2) Drive efficiency (%) All DT ablator DT/CH ablator (See Logan, Perkins, Barnard, Phys. of Plasmas, 15, 07271, 2008). Coupling efficiency  fuel shell kinetic energy/ion beam energy

The Heavy Ion Fusion Virtual National Laboratory At 30 J/cm 2 (20 kJ/g), (Al) target center reaches 1.1 eV, density 2.1 g/cc at 0.6 ns. 0.6 ns 1.0 ns T T Density

Evolution of center of 3.5  thick Al foil over the heating phase (1 ns) using LEOS with maxwell construction

The Heavy Ion Fusion Virtual National Laboratory NDCX II will nominally operate at the Bragg peak using Lithium ions for WDM experiments Energy loss rate (MeV/mg cm 2 ) Energy/Ion mass (MeV/amu) 0.4 MeV/amu = NDCX II (planned ) (Bragg peak) MeV/amu = NDCX I (nuclear stopping plateau) Ion beam uniformity and fractional energy loss can be high if operate at Bragg peak (Larry Grisham, PPPL) (dEdX figure from L.C Northcliffe and R.F.Schilling, Nuclear Data Tables, A7, 233 (1970)) Enter foil at energy ~1.5 x E peak Exit foil at energy ~0.5 x E peak

The Heavy Ion Fusion Virtual National Laboratory From Enrique Henestroza's NDCXII talk May13, 2009

The Heavy Ion Fusion Virtual National Laboratory The nominal beam assumes a 30 J/cm MeV Li ion beam, corresponding to 20 kJ/g in Al (SRIM) SRIM HYDRA/ QEOS For HYDRA runs we assume the nominal beam results in 20 kJ/g in Al. This implies the simulated beam had a fluence of 20 J/cm 2 (instead of 30 J/cm 2 )

The Heavy Ion Fusion Virtual National Laboratory

Simulations show that an NDCX II double pulse experiment could confirm benefits of double pulsing Ion beam 1 mm 9 mm (1 ns) 50  Ion: Li + or Li ++ Target: Solid Ar Intensity: 30 J/cm2 (each pulse) Each pulse: 1 ns long 2nd pulse, 1ns after 1st Simulations by Siu Fai Ng (DISH; vdw EOS) (simulations by Vietzer indicate room temp Al foam also candidate)

The Heavy Ion Fusion Virtual National Laboratory In addition to target physics, NDCX II will serve as a platform for driver beam physics tests - RF Wobbler dynamics - beam bending - beam-plasma interactions Example of one module of driver: - unneutralized acceleration with bunch compression - neutralized bunch compression and final focus

The Heavy Ion Fusion Virtual National Laboratory We are proposing an ER LDRD that is relevant to Direct Drive coupling physics and NDCX II Heavy Ion Beam Approach to Inertial Fusion-Fission Hybrids (This LDRD proposal is one of two simultaneous, coordinated proposals being submitted at LLNL and LBNL) LLNL: John Barnard (PI), Alex Friedman, Wayne Meier, L. John Perkins, Ralph Moir, Michael Hay (UC Berkeley undergraduate) LBNL: Bernhard Ludewigt, Robert Budnitz, B. Grant Logan, Roger Bangerter, Andy Sessler, Per Peterson (UC Berkeley) LLNL Funding Request: FY10=375k$, FY11=375k$, FY12=375k$ LBNL Funding Request: FY10=290k$, FY11=290k$, FY12=290k$ What do the unique properties of ion beam acceleration, final focus, and ion deposition imply about ion-based fusion-fission hybrid concepts? Can low pulse energy (< ~0.5 MJ) heavy-ion-based direct drive targets be used for small entry-level hybrid (or inertial fusion energy) drivers? Can a thick liquid or wetted wall be used in a hybrid? What are the systematic tradeoffs between ion energy, ion mass, pulse energy, and target gain in hybrid systems?

The Heavy Ion Fusion Virtual National Laboratory Extras

The Heavy Ion Fusion Virtual National Laboratory Target temp. NDCX-1NDCX-2 Metallic foam experiments at GSI~0.5 eV Measure target temperature using a beam compressed both radially and longitudinally Low√ Thin target dE/dx, energy distribution, charge state, and scattering in a heated target Low√ Positive - negative halogen ion plasma experiment >0.4 eV√√ Two-phase liquid-vapor metal experiments √√ Critical point measurements>1.0?√ Ion deposition and coupling experiments>1.0√ Collapsing bubble experiments>1.0√ We have identified a series of warm dense matter experiments that can begin on NDCX-I at Temperature < 1 eV time

The Heavy Ion Fusion Virtual National Laboratory NDCX I now uses a suite of optical diagnostics

The Heavy Ion Fusion Virtual National Laboratory Heavy-ion-beam driven warm dense matter and fusion target interactions Temperature (K) Ion density (cm -3 ) HIF NDCX II NDCX I eV 1000 From National HEDP Task Force Report, NDCX II covers WDM region -- a region of large uncertainty in EOS EOS pressure variance for 2 eqs. of state in Al (R. Lee) Density - Temperature universe solid Al

The Heavy Ion Fusion Virtual National Laboratory