On thermonuclear ignition criterion at the National Ignition Facility
|
|
- Bathsheba Eleanor Floyd
- 5 years ago
- Views:
Transcription
1 On thermonuclear ignition criterion at the National Ignition Facility Baolian Cheng, Thomas J. T. Kwan, Yi-Ming Wang, and Steven H. Batha Los Alamos National Laboratory, Los Alamos, New Mexico 87545, USA Sustained thermonuclear fusion at the National Ignition Facility remains elusive. Although recent experiments approached or exceeded the anticipated ignition thresholds, the nuclear performance of the laser-driven capsules was well below predictions in terms of energy and neutron production. Such discrepancies between expectations and reality motivate a reassessment of the physics of ignition. We have developed a predictive analytical model from fundamental physics principles. Based on the model, we obtained a general thermonuclear ignition criterion in terms of the areal density and temperature of the hot fuel. This newly derived ignition threshold and its alternative forms explicitly show the minimum requirements of the hot fuel pressure, mass, areal density, and burn fraction for achieving ignition. Comparison of our criterion with existing theories, simulations, and the experimental data show that our ignition threshold is more stringent than those in existing literature and that our results are consistent with the experiments. PACS numbers: 5.57, -z, r, b I. INTRODUCTION Recent National Ignition Campaign (NIC) experiments [] at the National Ignition Facility (NIF) achieved nearly 95% of the required peak implosion velocity, and the total areal density of the fuel was greater than the ignition threshold of g/cm [, 3]. Yet, the nuclear performance of the capsule was well below that needed for ignition: neutron outputs was at least two orders of magnitude below expectation, the energy observed in the hot deuterium-tritium (DT) was only /7th the total energy in the capsule [4, 5]. Such discrepancies motivate us to reexamine the physics of ignition. Researchers [,,6-4] have for decades developed criteria for the onset of thermonuclear ignition in inertial confinement fusion (ICF) approaches. The Lawson criterion is the classic example, expressed through physically measurable quantities such as the hot spot ion temperature T, pressure P, confinement time τ c, and areal density ρr of the DT fuel. Here, we derive a general thermonuclear burn criterion for sustained burn in the hot spot of the NIC capsule design and, in turn, an ignition threshold in terms of measurable physical quantities. To facilitate comparison with experimental results, we also derive alternative expressions for the ignition threshold in terms of other quantities, for example, the minimum required hot fuel pressure, mass, and burn fraction. The fundamental differences between our model and other theories and simulations are the distinction between the areal density of the hot spot (ρr) hs and the total areal density of the capsule (ρr) tot, and our definition of confinement time for thermonuclear (TN) ignition. We take the confinement time to be the hydrodynamic disassembly time, i.e., the hot spot radius divided by the effective sound speed in the hot spot. Other models [, 4, ] use a deceleration time taken as the ratio of the radius of the cold DT fuel and the peak implosion velocity[4]. The use of the deceleration time as the confinement time overestimates the TN burn time in the capsule leading to an overly optimistic criterion because the peak implosion velocity is less than the sound speed and the radius of the cold DT is nearly twice the radius of the hot spot at maximum implosion. II. IGNITION CRITERION The ignition condition for ICF capsules can be determined by energy balance principles, specifically, by two time scales[5]: the nuclear fusion reproduction time (τ rep = E T /Ė) and the hydrodynamic disassembly time (τ H = R hs /C s ), where E T = (3/)(n D +n T )kt +E rad is the total energy density of the hot DT fuel in which k is the Boltzmann constant and E rad the radiation energy density. Ė = n T n D < σv > DT W α is the energy deposition rate by fusion reactions, where W α is the energy deposited into the hot DT per fusion, which normally equals to a fraction (f α ) of the α-particle kinetic energy of 3.5 MeV. In this work, we choose f α =. The neutron energies are assumed escaped because the mean free path of the 4 MeV neutrons is much larger than the hot spot radius R hs. For the disassembly time, C s is the adiabatic sound speed. To account for the tamping effect by the cold fuel, we replace the sound speed with an effective sound speed Cs C s /f T, where f T ρ p /ρ hs [0] is the tamping factor, and ρ p and ρ hs are the mass density of the pusher and the hot spot at the interface between the hot and cold fuel, respectively. Other discussions on tamping factor can be found in []. In practice, energy losses are inevitable, and the net energy deposition rate can be written as Ė = n T n D < σv > DT W α i dqi l /dt, where superscript i denotes various losses, such as the energy loss by electron bremsstrahlung, dq b l /dt = C ρ DT T / and the heat outflux by electron conduction, dq e l /dt = C T 3.35 /Rhs [7], where C 9. 0 erg-cm 3 /(kev / g s), C 6.9
2 0 Power index n <σv> ~ T n T (kev) FIG.. The power index fitting of < σv > DT T n vs. temperature. 0 9 erg/(kev 3.35 cm-s), and T is in kev. These energy loss expressions were obtained in the approximation of the total yield of the bremsstrahlung[7], which are slightly different from the general bremsstrahlung radiation loss, C = Z 3 /A DT ergcm 3 /(kev / g s)[0], and the general heat conduction loss rate Q e l C T 3.5 /Rhs, C 8.87 ln Λ 09 erg/(kev 3.5 cm-s)[0] in use. Here Z is the ionization state and ln Λ is the Coulomb logarithm depending on the cut-off parameters. These general expressions would lead to a higher ignition threshold. Ignition occurs when τ rep /τ H, the condition for sustained TN burn of the hot spot. This condition gives a threshold for the areal density of the hot DT (ρr) hs [( + d) /d][3kt + E rad /n DT ]C sa DT /N A < σv > DT W α ( Q b l + Q e l )( + d) /(dn DT ), () where n DT n D + n T = ρ DT N A /A DT, Q i l dqi l /dt (i = b, e), d = D/T is the D to T ratio, N A Avogadro s number, and A DT the atomic weight mass of the DT mixture. Nuclear reactivity < σv > DT [6] can be approximated by a power law of the temperature, T n, with the power index n dependent on the temperature as shown in Fig.. In the temperature range 0. 6 kev, n (0.3/T /3 )/3[7]. For temperature range kev, < σv > DT C DT T 4 is a good approximation as shown in Fig., where C DT cm 3 /s/kev 4. It is evident from Eq. () that any energy loss increases the areal density threshold for ignition. Furthermore, with the denominator being positive and definite, it leads to two important observations: () for d =, the energy loss by bremsstrahlung emission prevents ignition at temperatures below T min = {[4C /(C DT W α )](A DT /N A ) } /7 3 kev at any (ρr) hs, and () the energy loss through electron heat conduction makes ignition impossible at any temperature when (ρr) hs < {[4C /(C DT W α )](A DT /N A ) T 0.65 } / 0.3 g/cm. These constraints may only be improved if the burn is in equilibrium when the bremsstrahlung and inverse-bremsstrahlung emission balance such that the associated energy loss is small relative to the heat <σv> /(at b ) a=.37e-0, b=4 a=.5e-0, b=3.9 a=.3e-0, b=4 a=.3e-0, b= T (kev) FIG.. The power law at b fit of < σv > DT vs. temperature. The black solid line represents a = and b = 4, red dot-dashed line for a = and b = 3.98, black dashed line for a = and b = 3.9, and blue dotted line for a = and b = 4, where T is in kev. capacity of the blackbody radiation loss. For simplicity and comparison purpose, hereafter, our theoretical model assumes spherical symmetry with no mix, no energy loss from bremsstrahlung or electron heat conduction, and a blackbody radiation energy loss (E rad at 4, where a is the radiation energy constant) from the hot DT into a compressing shell. It is obvious that any asymmetry will make ignition more difficult. Thus, Eq. () becomes (ρr) hs ( + d) d [3kT + at 4 /n DT ]C s A DT < σv > DT W α N A, () which gives ignition curves on the ρr-t plane under various conditions, as shown in Fig. 3. The general threshold depends on the ratio of D to T and is minimum at d =. Equation () suggests two ways to achieve ignition: () low ρr at high temperature, or () high ρr at low temperature. The NIC ignition design point is at (ρr) hs 0.3 g/cm and T 4 kev []. For d =, substituting the approximation < σv > DT T 4 into Eq. () and ignoring the radiation energy, Eq. () becomes (ρr) hs 4 κc f T ( T kev ).5 g/cm (3) for 3 kev < T < 5.5 kev, where κ c /C DT 5.54 is a constant depending on the power law fitting approximation for < σv > DT. Any departure from the ideal condition, such as asymmetry, a decrease in α-particle energy deposition, or radiation and other energy losses would lead to higher TN threshold and therefore greater difficulty in achieving ignition. Figure 3 shows various ignition curves at f T = on the ρr-t plane, showing that inclusion of the radiation heat capacity significantly raises the ignition threshold at temperatures above 3 kev. Below 3 kev, achieving ignition in an equilibrium mode is only feasible at high areal density. For reference, we have also plotted the ignition curve with the contributions of electron bremsstrahlung
3 3 III.a Lawson criterion and ignition parameter Substituting ρ hs = A DT P/RT (R is the gas constant) and R hs C s τ H into Eq. () gives the Lawson criterion P (Gbar)τ H(µs) > κ c ( + d) A DT d γg / T (kev), (4) FIG. 3. The ignition curve on the ρr-t plane for f T =. The ignition curve on the ρr-t plane above separates out the ignition region. The black curve represents the ignition criterion in Eq. () when the radiation term is neglected. Both the red and green curves show the impacts of the radiation term with ρ hs = g/cm 3 and ρ hs = 3 g/cm 3, respectively. The maroon dot-dashed line includes the contributions from both electron bremsstrahlung and heat conductions. Clearly, inclusion of radiation will make ignition more difficult. The dashed blue curve is the analytic solution in Eq. (3) for the NIC design. The red dots denote the D numerical calculations performed by Betti et al. [3]. and heat conductions in Fig. 3, which shows a more stringent ignition space in temperature (i.e., T min > 3. kev). We emphasize that, for a given temperature, the most critical metric characterizing the ICF ignition threshold is the areal density of the hot fuel, not the total areal density of the fuel. The total areal density is the sum of the areal densities of the hot spot and the surrounding cold DT fuel. It is obvious that a sustained TN burn of the hot spot must be maintained in order to light the cold fuel. The formation of hot spot in a capsule is complicated and depends on experimental conditions. Any relation between the hot spot mass and the total fuel mass is at best approximate. Therefore, it is misleading to use the total areal density of the fuel to characterize the ignition threshold or as an optimal design parameter for ignition. III. APPLICATIONS The physical applications of our ignition criterion are straightforward. From Eq. (), we can derive various alternative requirements, such as the minimum hot spot fuel pressure, mass, and burn fraction required for ignition. which is independent of f T. Here we have used C s (γ g RT/A DT ) / γ g T (kev )cm/s. For d = and γ g = 5/3, substituting κ c = 5.54 into the above equation gives P (Gbar)τ H (µs) 0.475/T (kev). At T = 4 kev and R hs 30µm, for example, the required minimum hot spot pressure would be 70 Gbar, which is more stringent than (nearly three times) the ignition conditions given by Betti et al. [4]. The essential difference between our model and that developed by Betti et al. is the physical definition of the confinement time. Using Eq. (3), one can define the ignition parameter for the NIC design χ d κ c( + d) f T (ρr) hs T (kev).5. (5) Ignition requires χ. For d =, the expression becomes 0.045f T (ρr) hs T (kev).5. At T = 4 kev, the ignition condition becomes (ρr) hs 0.69f T g/cm. To compare with NIC experiments, we apply the scaling relationship between (ρr) hs and the total areal density of the fuel, (ρr) tot, derived in [5], (ρr) hs = (ρr) tot ψ/(+ψ). Letting the adiabatic index of the cold fuel (γ p ) and hot fuel (γ g ) be 5/3, Eq. (5) becomes χ = d κ c ( + d) f ψ T + ψ (ρr) tott (kev).5, (6) where ψ ηvimp /ϵ hs is the ratio of the specific implosion energy (ηvimp /) to the specific internal energy (ϵ hs = 3RT/A DT ) of the hot fuel. Here, V imp is the peak implosion velocity and η the implosion energy efficiency[5]. For V imp 370 km/s and T=4keV, ψ 0.48, (ρr) tot 5.35 g/cm for ignition if f T = d = η =. This is in sharp contrast to the NIC ignition design requiring (ρr) tot > g/cm [, ] and the Betti et al. D criterion from D simulations χ (ρr) 0.8 tot[t (kev)/4.4].8 [4], which gives (ρr) tot.4 g/cm at T = 4 kev. Again, our model shows a significant increase in the ρr requirement for ignition, which is consistent with the NIC data where < (ρr) tot < 5.35g/cm were achieved. In the NIC experiments, the total areal density of the fuel is a measurable quantity through the measured down scattering neutron ratio (DSR), (ρr) tot DSR [4, 8]. For example, at DSR and T 3. kev, as in shot N03, (ρr) tot.3g/cm, the inferred (ρr) hs 0.47g/cm and P τ 4.4 atm-s according to the formula in [4]. For shot N39, DSR 0.04, T 5 kev[9], and χ.. These results exceed the ignition thresholds and would predict ignition
4 4 of the capsule. However the neutron yield of the capsule (Y n and ) was far below ignition. In contrast, according to our model the areal density of the hot spot for N03 was only 0. g/cm, and the ignition parameter χ was at f T =. Similarly, for N39, (ρr) hs 0.077g/cm and χ These values are far below our ignition criterion, (ρr) hs 0.69 g/cm for f T = and (ρr) hs 0.35 g/cm for f T =, which is consistent with the low output from the capsule. Function ψ is sensitive to the adiabat and equation state of the pusher (mainly cold fuel). For the same required hot spot areal density for ignition, if the pusher were cold and hard, for example, γ p =.0 and γ g = 5/3, ψ 0.944, then the required total areal density for achieving ignition at the same conditions (V imp = 370 km/s and T = 4 kev) can be reduced from 5.35 g/cm to 4.4 g/cm. One of the most important difference between the criterion from our model and the one used in NIC is the use of the fuel areal density: (ρr) hs vs. (ρr) tot. Our model focuses on the hot fuel and uses the areal density of the hot spot as the fuel areal density in the derivation because the necessary and sufficient condition for achieving ignition is to have a sustainable TN burn in the hot spot. The sustained burn can then light the cold fuel under the right conditions resulting in TN ignition. III.b Minimum hot spot mass and burn fraction Sustaining TN burn in the hot spot and achieving ignition for a given design (e.g., laser energy and convergence ratio) require a minimum hot fuel mass. This minimum mass can be obtained from the ignition condition (), and for T = kev, can be expressed M min hs 4π 3 κ c ( + d) R0F f T T (kev).5 d Cf, (7) where C f R 0F /R hs is the geometric convergence ratio, and R 0F and R hs are, respectively, the initial inner radius of the fuel and the final radius of the hot spot. The ignition parameter given by Eq. (5) provides a measure of how far a given design is from ignition. At d =, T = 4 kev, R 0F = 000 µm, and C f 35, as in the NIC design, the minimum hot spot mass from Eq. (7) is about 4 µg if f T =. For C f 7, as in the recent high-foot shots at NIF, the minimum hot spot mass is 40. µg if f T =. The minimum hot spot mass for ignition given here is nearly four times the hot spot mass observed in NIF experiments. For example, M hs was only 3.9 µg in the low-foot shot N03 [4] and 7. µg in the highfoot shot N3097 [0]. Again, our model is consistent with observation of non-ignition. We point out that although the required minimum hot fuel mass is decreasing dramatically when the convergence ratio is increasing, the instabilities at the interface Burn parameter ζ T (g/cm ) T (kev) τ c ~τ H τ c ~τ H /3 τ c ~τ H /4 FIG. 4. The burn parameter vs. temperature.. ϕ ϕ between the cold and hot fuel grow nonlinearly with C f [3]. Thus, for high-convergence capsules, the greatest challenge is to achieve a hot, clean spot in the fuel. The burn fraction that characterizes the TN burn is defined as the ratio ϕ N fus /NDT 0, with N fus being the total number of fusion reactions and NDT 0 the number of DT pairs initially present in the fuel, and can be expressed as = N 0 DT < σv > τ c, where the nuclear confiement time τ c is defined as the time during which the fuel is maintained at a temperature above the critical ignition temperature to sustain the fusion reaction. If we assume τ c to be at least the hydrodynamic disassembly time τ H, the required burn fraction of the hot fuel for sustained TN burn is derived from ignition condition () and given by ϕ min DT (ρr) hs ζ T (T ) + (ρr) hs, (8) where ζ T (T ) ( +d d )( A DT C s N A <σv> ) is a burn parameter that varies with the temperature of the hot fuel. The burn parameter, ζ T, has values of 99 at T = 4 kev and between 4 and 8 g/cm at 0 kev < T <5 kev for f T = as shown in Fig. 4. The minimum burn fraction can also be approximately expressed in terms of the ion temperature of the hot spot, ϕ min DT ( + d)(3kt + at 4 /n)/w α. Table I lists the required minimum burn fractions at different temperatures for d =. At 4 kev, the hot spot burn frac- T (kev) ζ T (g/cm ) (ρr) hs (g/cm ) ϕ min DT (%) TABLE I. Burn parameter, (ρr) hs d = f T = with no radiation. and ϕ min DT vs. T at tion needed for ignition is ϕ > 0.677%. NIF experiments reached only a small fraction of this value. For example, the low-foot shot N5, which had the highest yield of the NIC shots ( neutrons) only achieved % of the required burn fraction, while the burn frac-
5 where M p is the mass of the pusher at peak implosion velocity[5] and τ B is the burn width. We have applied this formula to a series of NIC and NIF experiments. Table II lists the shots that we considered in this paper and the physical parameters associated with each shot. Table III summarizes the results, showing Shot # M p V imp T hs τ B ν (µg) (cm/s) (kev) (ns) N N N N FIG. 5. The minimum required burn fraction and areal density of the hot spot for ignition vs. the ion temperature. tion of the high-foot shot N3097 ( neutrons) was only 4% of that required for ignition [9]. Fig. 5 shows the minimum burn fraction and the corresponding minimum areal density of the hot spot required for ignition as a function of the ion temperature. Clearly, both the burn fraction and burn parameter are very sensitive to the fuel temperature and areal density. The lower the hot spot areal density, the larger the burn fraction required. Again, we emphasize that the areal density ρr in the burn fraction equation, Eq. (8), is the areal density of the hot fuel (ρr) hs, not the total areal density (ρr) tot. The latter overestimates the burn fractions in NIC capsules. The two areal densities are equivalent only when the burn front has propagated through and heated all the fuel. III.c Neutron yield The neutron yield of the capsule can be estimated by the formula Y n = τ B V 0 0 n Dn T < σv > dv dt, where V is the volume of the hot fuel. For NIF experiments, V corresponds to the volume of the hot spot. Substituting the implosion scaling laws derived in [5] into the above equation yield Y n d ( + d) ( N A (γ p )(γ g ) R ) (3γ p ) ηc DT M p V impp τ B T kev, in the c.g.s system units except for T is in kev. For convenience, letting d = η = Eq. (9) can be further reduced to Y n (γ p )(γ g ) ( M p (3γ p ) µg )( V imp P τ B km/s ) ( Gbar.ns )T kev, (0) (9) TABLE II. Physical parameters in the NIF shots. Where ν A DT Vimp/(RT ) 0.96Vimp/T is a model parameter, in which V imp is in 00km/s and T is in kev. good agreements between Eq. (0) and the experimental data, where γ g = 5/3, η = and Table II were used. Shot # γ p DSR (ρr) hs P τ B Y n(0 4 ) Y n(0 4 ) (%) (g/cm ) (Gb.ns) (theo.) (obs.) N005 5/ N03 4/ N3050 5/ N3097 5/ TABLE III. Yield comparison between theory and experimental data at NIF. Here we have used the upper bound of DSR for shot N3097 to match the inferred hot spot areal density (ρr) hs 0. g/cm [0]. CONCLUSION In summary, we developed a general analytical ignition criterion in Eq. () for ICF capsules under the assumptions of perfect symmetry and no mix. Our thermonuclear burn criterion was derived by balancing the DT fusion heating time with the hydrodynamic disassembly time. By ignoring energy loss processes and radiation, we arrive at a simplified expression of the ignition criterion for NIF design in Eq. (3). Our recent D LASNEX calculations starting with an assembly of hot fuel with predetermined areal densities and temperatures but including losses (electron heat conduction and bremsstrahlung) during its TN reaction show that our ignition threshold under ideal conditions is optimistic as we anticipated. However we found that the ignition criterion in Eq. (3) is still more stringent than that used in the NIF design. The threshold values given by Eqs. (3-8) are consistently more than three times higher than those in existing literature. The fundamental differences between these criteria are reflected in the relevant use of (ρr) hs vs. (ρr) tot
6 6 for ignition and the definition of confinement time. Note that the general expression of the ignition criterion given in Eq. () includes energy losses. A numerical solution of Eq. () taking into account of the energy losses will further enhance the predictive capability of our analysis. ACKNOWLEDGEMENTS The authors wish to thank the referee for many insightful and constructive comments that led to notable improvement of our manuscript. The authors are grateful to P. Amendt, C. Cerjan, D. Clark, S. Haan, P. Patel, H. Robey, B. Tipton for sharing the NIC data, analysis, and to B. Albright, N. Hoffman, J. Mercer-Smith, K. Molvig, J. Pedicini, A. Simakov, C. Snell and D. Wilson for helpful discussions and to C.S. Carmer for editing this article. This work was performed under the auspices of the U.S. Department of Energy by the Los Alamos National Laboratory under Contract No. W-7405-ENG-36. [] J. Lindl, O. Landen, J. Edwards, E. Moses and NIC Team (with erratum pending), Phys. Plasmas, 0050 (04). [] J. Edward, J. D. Lindl, B. K. Spears, S. V. Weber, L. J. Atherton, D. L. Bleuel, D. K. Bradley, D. A. Callahan, C. J. Cerjan, D Clark, G. W. Collins, J. E. Fair, R. J. Fortner, S. H. Glenzer, S. W. Haan, B. A. Hammel, A. V. Hamza, S. P. Hatchett, N. Izumi, B. Jacoby, O. S. Jones, J. A. Koch, B. J. Kozioziemski, O. L. Landen, R. Lerche, B. J. MacGowan, A. J. MacKinnon, E. R. Mapoles, M. M. Marinak, M. Moran, E. I. Moses, D. H. Munro, D. H. Schneider, S. M. Sepke, D. A. Shaughnessy, P. T. Springer, R. Tommasini, L. Bernstein, W. Stoeffl, R. Betti, T. R. Boehly, T. C. Sangster, V. Yu. Glebov, P. W. McKenty, S. P. Regan, D. H. Edgell, J. P. Knauer, C. Stoeckl, D. R. Harding, S. Batha, G. Grim, H. W. Herrmann, G. Kyrala, M. Wilke, D. C. Wilson, J. Frenje, R. Petrasso, K. Moreno, H. Huang, K. C. Chen, E. Giraldez, J. D. Kilkenny, M. Mauldin, N. Hein, M. Hoppe, A. Nikroo and R. J. Leeper, Phys. Plasmas 8, (0). [3] S. W. Haan, J. D. Lindl, D. A. Callahan, D. S. Clark, J. D. Salmonson, B. A. Hammel, L. J. Atherton, R. C. Cook, M. J. Edwards, S. Glenzer, A. V. Hamza, S. P. Hatchett, M. C. Herrmann, D. E. Hinkel, D. D. Ho, H. Huang, O. S. Jones, J. Kline, G. Kyrala, O. L. Landen, B. J. MacGowan, M. M. Marinak, D. D. Meyerhofer, J. L. Milovich, K. A. Moreno, E. I. Moses, D. H. Munro, A. Nikroo, R. E. Olson, K. Peterson, S. M. Pollaine, J. E. Ralph, H. F. Robey, B. K. Spears, P. T. Springer, L. J. Suter, C. A. Thomas, R. P. Town, R. Vesey, S. V. Weber, H. L. Wilkens, and D. C Wilson, Phys. Plasmas 8, 0500 (0). [4] D. S. Clark, D.E. Hinkel, D. C. Eder, O. S. Jones, S. W. Haan, B. A. Hammel, M. M. Marinak, J. L. Milovich, H. F. Robey, L. J. Suter, and R. P. J. Town, Physics of Plasmas 0, (03). [5] C. J. Cerjan, P. T. Springer and S. M. Sepke, Phys. Plasma 0, (03). [6] J. D. Lawson, Proc. Phys. Soc. London, Sect. B 70, 6 (957). [7] E. N. Avrorin, L. P. Feoktistov and L. I. Shibarshov, Sov. J. Plasma Phys., 6(5), 57, 980. [8] B. V. Litvinov, N. V. Ptitsyna, V. I. Chitaikin and L. I. Shibarshov, Physics-Doklady 336, 9 (994). [9] J. D. Lindl, Inertial Confinement Fusion, Springer, 998. [0] S. Atzeni and J. Meyer-Ter-Vehn, The Physics of Inertial Fusion, Oxford, 004. [] M. Mahdavi and A. Gholami, Plasma Sci. and Technol. 5, 33(03). [] J. Edwards et al., P. K. Patel, J. D. Lindl, L. J. Atherton, S. H. Glenzer, S. W. Haan, J. D. Kilkenny, O. L. Landen, E. I. Moses, A. Nikroo, R. Petrasso3, T. C. Sangster4, P. T. Springer, S. Batha5, R. Benedetti, L. Bernstein, R. Betti4, D. L. Bleuel, T. R. Boehly4, D. K. Bradley, J. A. Caggiano, D. A. Callahan, P. M. Celliers, C. J. Cerjan, K. C. Chen, D. S. Clark, G. W. Collins, E. L. Dewald, L. Divol, S. Dixit, T. Doeppner, D. H. Edgell4, J. E. Fair, M. Farrell, R. J. Fortner, J. Frenje3, M. G. Gatu Johnson3, E. Giraldez, V. Yu. Glebov4, G. Grim5, B. A. Hammel, A. V. Hamza, D. R. Harding4, S. P. Hatchett, N. Hein, H. W. Herrmann5, D. Hicks, D. E. Hinkel, M. Hoppe, W. W. Hsing, N. Izumi, B. Jacoby, O. S. Jones, D. Kalantar, R. Kauffman, J. L. Kline5, J. P. Knauer4, J. A. Koch, B. J. Kozioziemski, G. Kyrala5, K. N. LaFortune, S. Le Pape, R. J. Leeper, R. Lerche, T. Ma, B. J. MacGowan, A. J. MacKinnon, A. Macphee, E. R. Mapoles, M. M. Marinak, M. Mauldin, P. W. McKenty, M. Meezan, P. A. Michel, J. Milovich, J. D. Moody, M. Moran, D. H. Munro, C. L. Olson, K. Opachich, A. E. Pak, T. Parham, H.-S. Park, J. E. Ralph, S. P. Regan, B. Remington, H. Rinderknecht, H. F. Robey, M. Rosen, S. Ross, J. D. Salmonson, J. Sater, D. H. Schneider, F. H. Sguin, S. M. Sepke, D. A. Shaughnessy, V. A. Smalyuk, B. K. Spears, C. Stoeckl, W. Stoeffl, L. Suter, C. A. Thomas, R. Tommasini, R. P. Town, S. V. Weber, P. J. Wegner, K. Widman, M. Wilke, D. C. Wilson, C. B. Yeamans and A. Zylstra, Phy. Plasmas 0, (03). [3] C. D. Zhou and R. Betti, Phys. Plasmas 5, 0707 (008); Phys. Plasmas 4, (007). [4] R. Betti, P.Y. Chang,, B. K. Spears, K. S. Anderson, J. Edwards, M. Fatenejad, J. D. Lindl, R. L. McCrory, R. Nora, and D. Shvarts, Phys. Plasmas 7, 0580 (00). [5] B. Cheng, T.J.T. Kwan, Y.-M. Wang and S. H. Batha, Phys. Rev. E 88, 040 (03). [6] G. R. Caughlan and W. A. Fowler, Atomic data and nuclear data tables 40, (988). [7] R. Chrien, Private communication, 04; H.-S. Bosch and G. M. Hale, Nucl. Fusion 3, 6 (99). [8] J.M. Gatu, J.A. Frenje, D.T. Casey, C.K.Li, F.H. Sguin, R. Petrasso, R. Ashabranner, R.M. Bionta, D.L. Bleuel, E.J. Bond, J.A. Caggiano, A. Carpenter, C.J. Cerjan, T.J. Clancy, T. Doeppner, M.J. Eckart, M.J. Edwards,
7 7 S. Friedrich, S.H. Glenzer, S.W. Haan, E.P. Hartouni, R. Hatarik, S.P. Hatchett, O.S. Jones, G. Kyrala, S. Le Pape, R.A. Lerche, O.L. Landen, T. Ma, A.J. MacKinnon, M.A. McKernan, M.J. Moran, E. Moses, D.H. Munro, J. McNaney, H.S. Park, J. Ralph, B. Remington, J.R. Rygg, S.M. Sepke, V. Smalyuk, B. Spears, P.T. Springer, C.B. Yeamans, M. Farrell, D. Jasion, J.D. Kilkenny, A. Nikroo, R. Paguio, J.P. Knauer, V.Y. Glebov, T.C. Sangster, R. Betti, C. Stoeckl, J. Magoon, M.J.3rd Shoup, G.P. Grim, J. Kline, G.L. Morgan, T.J. Murphy, R.J. Leeper, C.L. Ruiz, G.W. Cooper, A.J. Nelson. Rev. Sci. Instrum. 83, 0D308 (0). [9] H.-S. Park O.A. Hurricane, D.A. Callahan, D.T. Casey, E.L. Dewald, T.R. Dittrich, T. Dppner, D.E. Hinkel, L.F. Berzak Hopkins, S. Le Pape, T. Ma, P.K. Patel, B.A. Remington, H.F. Robey, J.D. Salmonson, and J.L. Kline, Phys. Rev. Lett., (04); [0] O. A. Hurricane, D. A. Callahan, D. T. Casey, P. M. Celliers, C. Cerjan, E. L. Dewald, T. R. Dittrich, T. Dppner, D. E. Hinkel, L. F. Berzak Hopkins, J. L. Kline, S. Le Pape, T. Ma, A. G. MacPhee, J. L. Milovich, A. Pak, H.- S. Park, P. K. Patel, B. A. Remington, J. D. Salmonson, P. T. Springer and R. Tommasini, Nature, 3008 (04). [] R. Betti, C. D. Zhou, K. S. Anderson, L. J. Perkins, W. Theobald, and A. A. Solodov, Phys. Rev. Lett. 98, 5500 (007). [] J. Nuckolls and Y.-L. Pan, UCRL-75876, Lawrence Livermore Laboratory [3] K. O. Mikaelian, Phys. Rev. A 4, 3400 (990)
8 T (kev) 9 8 <σv> ~ T n Power index n
9 T (kev) a=.37e-0, b=4 a=.5e-0, b=3.9 a=.3e-0, b=4 a=.3e-0, b=3.98 <σv> /(at b )
10 (ρr) DT (g/cm ) Matter dominated (T i =T e ) + radiation (T i =T e =T r, ρ hs =) + radiation (T i =T e =T r, ρ hs =3) Analytic solution (T i =T e ) D simulations (Zhou & Betti) + bremsstrahlung + e-conduction T peak (kev)
11 T (kev) Burn parameter ζ T (g/cm ) 00 0 τ c ~τ H τ c ~τ H /3 τ c ~τ H /4
12 Areal density (g/cm ) or Burn fraction Minimum ρr (g/cm ) Burn fraction φ=ρr/(ζ T +ρr) Peak no-burn temperature (kev)
Measurements of collective fuel velocities in deuterium-tritium exploding pusher and cryogenically layered deuterium-tritium implosions on the NIF
Measurements of collective fuel velocities in deuterium-tritium exploding pusher and cryogenically layered deuterium-tritium implosions on the NIF M. Gatu Johnson, D. T. Casey, J. A. Frenje, C.-K. Li,
More informationSimultaneous measurement of the HT and DT fusion burn histories in inertial fusion implosions
Simultaneous measurement of the HT and DT fusion burn histories in inertial fusion implosions A.B. Zylstra,, a) H.W. Herrmann, Y.H. Kim, A.M. McEvoy,, b) M.J. Schmitt, G. Hale, C. Forrest, V.Yu. Glebov,
More informationThe Near Vacuum Hohlraum campaign at the NIF: a new approach
The Near Vacuum Hohlraum campaign at the NIF: a new approach S. Le Pape, 1 L. F. Berzak Hopkins, 1 L. Divol, 1 N. Meezan, 1 D. Turnbull, 1 A. J. Mackinnon, 2 D. Ho, 1 J.S. Ross, 1 S. Khan, 1 A. Pak, 1
More informationGamma Reaction History ablator areal density constraints upon correlated diagnostic modeling of NIF implosion experiments
Gamma Reaction History ablator areal density constraints upon correlated diagnostic modeling of NIF implosion experiments C. Cerjan, 1, a) D. B. Sayre, 1 O. L. Landen, 1 J. A. Church, 1 W. Stoeffl, 1 E.
More informationSimulations of indirectly driven gas-filled capsules at the National Ignition Facility
Simulations of indirectly driven gas-filled capsules at the National Ignition Facility S. V. Weber, 1 D. T. Casey, 1 D. C. Eder, 1 J. D. Kilkenny, 5 J. E. Pino, 1 V. A. Smalyuk, 1 G. P. Grim, 2 B. A. Remington,
More informationThe Pursuit of Indirect Drive Ignition at the National Ignition Facility
The Pursuit of Indirect Drive Ignition at the National Ignition Facility Workshop on Plasma Astrophysics: From the Laboratory to the Non-Thermal Universe Oxford, England July 3-5, 2017 Richard Town Deputy
More informationIn-flight observations of low-mode R asymmetries in NIF implosions
In-flight observations of low-mode R asymmetries in NIF implosions The MIT Faculty has made this article openly available. Please share how this access benefits you. Your story matters. Citation As Published
More informationHigh-Performance Inertial Confinement Fusion Target Implosions on OMEGA
High-Performance Inertial Confinement Fusion Target Implosions on OMEGA D.D. Meyerhofer 1), R.L. McCrory 1), R. Betti 1), T.R. Boehly 1), D.T. Casey, 2), T.J.B. Collins 1), R.S. Craxton 1), J.A. Delettrez
More informationEffects of fuel-capsule shimming and drive asymmetry on inertial-confinement-fusion symmetry and yield
PSFC/JA-16-43 Effects of fuel-capsule shimming and drive asymmetry on inertial-confinement-fusion symmetry and yield F. H. Séguin, 1 C. K. Li, 1 J. L. DeCiantis, 1 J. A. Frenje, 1 J. R. Rygg, 1 R. D. Petrasso,
More informationDemonstrated high performance of gas-filled rugby-shaped hohlraums on Omega
Demonstrated high performance of gas-filled rugby-shaped hohlraums on Omega F. Philippe, V. Tassin, S. Depierreux, P. Gauthier, P. E. Masson-Laborde, M. C. Monteil, P. Seytor, B. Villette, B. Lasinski,
More informationProgress in detailed modelling of low foot and high foot implosion experiments on the National Ignition Facility
Journal of Physics: Conference Series PAPER OPEN ACCESS Progress in detailed modelling of low foot and high foot implosion experiments on the National Ignition Facility Related content - Capsule modeling
More informationHigh-density carbon ablator ignition path with low-density gas-filled rugby hohlraum
High-density carbon ablator ignition path with low-density gas-filled rugby hohlraum Peter Amendt, Darwin D. Ho and Ogden S. Jones Lawrence Livermore National Laboratory, Livermore CA 94551 A recent low
More informationDesign of a Peanut Hohlraum with Low Gas-Fill Density for the Laser Megajoule
Design of a Peanut Hohlraum with Low Gas-Fill Density for the Laser Megajoule X. Li ( 李欣 ) *, C. S. Wu ( 吴畅书 ), Z. S. Dai ( 戴振生 ), D. G. Kang ( 康洞国 ), W. D. Zheng ( 郑无敌 ), P. J. Gu ( 古培俊 ), P. Song ( 宋鹏
More informationFukuoka, Japan. 23 August National Ignition Facility (NIF) Laboratory for Laser Energetics (OPERA)
Fukuoka, Japan 23 August 2012 National Ignition Facility (NIF) LLNL-PRES-562760 This work was performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under
More informationPerformance of beryllium targets with full-scale capsules in low-ll 6.72-mm hohlraums on the National Ignition Facility
Performance of beryllium targets with full-scale capsules in low-ll 6.72-mm hohlraums on the National Ignition Facility A. N. Simakov, 1,a) D. C. Wilson, 1 S. A. Yi, 1 E. N. Loomis, 1 J. L. Kline, 1 G.
More informationHigh-resolution measurements of the DT neutron spectrum using new CD foils in the Magnetic Recoil
PSFC/JA-16-15 High-resolution measurements of the DT neutron spectrum using new CD foils in the Magnetic Recoil neutron Spectrometer (MRS) on the National Ignition Facility M. Gatu Johnson, J.A. Frenje,
More informationThe effect of shock dynamics on compressibility of ignition-scale National Ignition Facility implosions
The effect of shock dynamics on compressibility of ignition-scale National Ignition Facility implosions The MIT Faculty has made this article openly available. Please share how this access benefits you.
More informationhohlraum directly and reduce the effect of the beam phasing technology. A crossed-beam energy transfer (CBET) [1] technique is used to maintain the re
A new ignition hohlraum design for indirect-drive inertial confinement fusion Xin Li( 李欣 ) 1, Chang-Shu Wu( 吴畅书 ) 1, Zhen-Sheng Dai( 戴振生 ) 1,, Wu-Di Zheng( 郑无敌 ) 1, Jian-Fa Gu( 谷建法 ) 1, Pei-Jun Gu( 古培俊
More informationWhere are we with laser fusion?
Where are we with laser fusion? R. Betti Laboratory for Laser Energetics Fusion Science Center Dept. Mechanical Engineering and Physics & Astronomy University of Rochester HEDSA HEDP Summer School August
More informationUNIVERSITY OF ROCHESTER LABORATORY FOR LASER ENERGETICS. Volume 142 January March 2015 DOE/NA/ LLE Review.
UNIVERSITY OF ROCHESTER LABORATORY FOR LASER ENERGETICS Volume 142 January March 215 DOE/NA/1944-1219 LLE Review Quarterly Report About the Cover: The photo on the cover shows Prof. Riccardo Betti (front)
More informationICF ignition and the Lawson criterion
ICF ignition and the Lawson criterion Riccardo Betti Fusion Science Center Laboratory for Laser Energetics, University of Rochester Seminar Massachusetts Institute of Technology, January 0, 010, Cambridge
More informationDiagnosing magnetized liner inertial fusion experiments on Z a)
Diagnosing magnetized liner inertial fusion experiments on Z a) S. B. Hansen 1,b), M. R. Gomez 1, A. B. Sefkow 1, S. A. Slutz 1, D. B. Sinars 1, K. D. Hahn 1, E. C. Harding 1, P. F. Knapp 1, P. F. Schmit
More informationarxiv: v2 [physics.plasm-ph] 8 Oct 2015
Under consideration for publication in J. Plasma Phys. 1 arxiv:1508.00803v2 [physics.plasm-ph] 8 Oct 2015 Imposed magnetic field and hot electron propagation in inertial fusion hohlraums DAVID J. STROZZI
More informationThe Ignition Physics Campaign on NIF: Status and Progress
Journal of Physics: Conference Series PAPER OPEN ACCESS The Ignition Physics Campaign on NIF: Status and Progress To cite this article: M. J. Edwards and Ignition Team 216 J. Phys.: Conf. Ser. 688 1217
More informationThe Magnetic Recoil Spectrometer (MRSt) for time-resolved measurements of the neutron spectrum at the National Ignition Facility (NIF)
PSFC/JA-16-32 The Magnetic Recoil Spectrometer (MRSt) for time-resolved measurements of the neutron spectrum at the National Ignition Facility (NIF) J.A. Frenje 1 T.J. Hilsabeck 2, C. Wink1, P. Bell 3,
More informationEmpirical assessment of the detection efficiency of CR-39 at high proton fluence and a compact, proton detector for high-fluence applications
Empirical assessment of the detection efficiency of CR-39 at high proton fluence and a compact, proton detector for high-fluence applications M. J. Rosenberg, F. H. Séguin, C. J. Waugh, H. G. Rinderknecht,
More informationKinetic mix mechanisms in shock-driven inertial confinement fusion implosionsa)
Kinetic mix mechanisms in shock-driven inertial confinement fusion implosionsa) H. G. Rinderknecht, H. Sio, C. K. Li, N. Hoffman, A. B. Zylstra, M. J. Rosenberg, J. A. Frenje, M. Gatu Johnson, F. H. Séguin,
More informationImpact of First-Principles Properties of Deuterium Tritium. on Inertial Confinement Fusion Target Designs
Impact of First-Principles Properties of Deuterium Tritium on Inertial Confinement Fusion Target Designs S. X. Hu( 胡素兴 ) 1,*,, V. N. Goncharov, T. R. Boehly, R. L. McCrory,** and S. Skupsky Laboratory
More informationEffects of alpha stopping power modelling on the ignition threshold in a directly-driven Inertial Confinement Fusion capsule
Effects of alpha stopping power modelling on the ignition threshold in a directly-driven Inertial Confinement Fusion capsule M. Temporal 1, a, B. Canaud 2, W. Cayzac 2, R. Ramis 3, and R.L. Singleton Jr
More informationHydrodynamic instability measurements in DTlayered ICF capsules using the layered-hgr platform
Journal of Physics: Conference Series PAPER OPEN ACCESS Hydrodynamic instability measurements in DTlayered ICF capsules using the layered-hgr platform Related content - Mix and hydrodynamic instabilities
More informationElectron Temperature Measurements inside the Ablating Plasma of Gas-Filled. Hohlraums at the National Ignition Facility
Electron Temperature Measurements inside the Ablating Plasma of Gas-Filled Hohlraums at the National Ignition Facility M.A. Barrios 1, D.A. Liedahl 1, M.B. Schneider 1, O. Jones 1, G.V. Brown 1, S.P. Regan
More informationThe Hugoniot and chemistry of ablator plastic below 100 GPa
1 2 3 4 5 The Hugoniot and chemistry of ablator plastic below 100 GPa M. C. Akin, D. E. Fratanduono, and R. Chau Lawrence Livermore National Laboratory, Livermore, CA 94550 (Dated: January 7, 2016) The
More informationThe effect of residual kinetic energy on apparent ion temperature in ICF implosions. T. J. Murphy
LA-UR-15-27714 The effect of residual kinetic energy on apparent ion temperature in ICF implosions T. J. Murphy National ICF Diagnostics Working Group Meeting October 6-8, 2015 Outline Basic kinetics of
More informationPROGRESS OF INDIRECT DRIVE INERTIAL CONFINEMENT FUSION IN THE US
PROGRESS OF INDIRECT DRIVE INERTIAL CONFINEMENT FUSION IN THE US J. L. KLINE, 1 S. H. BATHA, 1 L. R. BENEDETTI, 2 D. BENNETT, 2 S. BHANDARKAR, 2 L. F. BERZAK HOPKINS, 2 J. BIENER, 2 M. M. BIENER 2, R BIONTA,
More informationPolar Drive on OMEGA and the NIF
Polar Drive on OMEGA and the NIF OMEGA polar-drive geometry 21.4 Backlit x-ray image OMEGA polar-drive implosion 21.4 58.2 77.8 42. 58.8 CR ~ 5 R = 77 nm 4 nm 4 nm P. B. Radha University of Rochester Laboratory
More informationHydrodynamic growth experiments with the 3-D, native-roughness modulations on NIF
Journal of Physics: Conference Series PAPER OPEN ACCESS Hydrodynamic growth experiments with the 3-D, native-roughness modulations on NIF To cite this article: V A Smalyuk et al 2016 J. Phys.: Conf. Ser.
More informationThe 1-D Cryogenic Implosion Campaign on OMEGA
The 1-D Cryogenic Implosion Campaign on OMEGA Yield Exp (#1 14 ) 1.4 1.2 1..8.6.4 1-D campaign neutron yields.2 R. Betti University of Rochester Laboratory for Laser Energetics.2.4.6.8 1. 1.2 LILAC 4 8.
More informationPolar-Direct-Drive Experiments with Contoured-Shell Targets on OMEGA
Polar-Direct-Drive Experiments with Contoured-Shell Targets on OMEGA F. J. Marshall, P. B. Radha, M. J. Bonino, J. A. Delettrez, R. Epstein, V. Yu. Glebov, D. R. Harding, and C. Stoeckl Laboratory for
More informationObservations of the collapse of asymmetrically driven convergent shocks. 26 June 2009
PSFC/JA-8-8 Observations of the collapse of asymmetrically driven convergent shocks J. R. Rygg, J. A. Frenje, C. K. Li, F. H. Seguin, R. D. Petrasso, F.J. Marshalli, J. A. Delettrez, J.P. Knauer, D.D.
More informationProgress in Direct-Drive Inertial Confinement Fusion Research at the Laboratory for Laser Energetics
1 Progress in Direct-Drive Inertial Confinement Fusion Research at the Laboratory for Laser Energetics R.L. McCrory 1), D.D. Meyerhofer 1), S.J. Loucks 1), S. Skupsky 1) R.E. Bahr 1), R. Betti 1), T.R.
More informationHigh Convergence, Indirect Drive Inertial Confinement Fusion Experiments at Nova
UCRL-JC-119536 PREPRNT High Convergence, ndirect Drive nertial Confinement Fusion Experiments at Nova R. A. Lerche, M. D. Cable, S. P. Hatchett, J. A. Carid, J. D. Kilkenny, H. N. Kornblum, S. M. Lane,
More informationThe National Ignition Campaign: Status and Progress
1 The National Ignition Campaign: Status and Progress E. I. Moses Lawrence Livermore National Laboratory, Livermore, CA 94450 Abstract. The National Ignition Facility (NIF) at Lawrence Livermore National
More informationarxiv: v1 [physics.plasm-ph] 12 Oct 2016
Simulation and assessment of ion kinetic effects in a direct-drive capsule implosion experiment A. Le, T. J. T. Kwan, M. J. Schmitt, H. W. Herrmann, and S. H. Batha arxiv:60.078v [physics.plasm-ph] Oct
More informationDiagnosing OMEGA and NIF Implosions Using the D 3 He Spectrum Line Width
Introduction Diagnosing OMEGA and NIF Implosions Using the D 3 He Spectrum Line Width A. B. Zylstra, M. Rosenberg, N. Sinenian, C. Li, F. Seguin, J. Frenje, R. Petrasso (MIT) R. Rygg, D. Hicks, S. Friedrich,
More informationInertial Confinement Fusion DR KATE LANCASTER YORK PLASMA INSTITUTE
Inertial Confinement Fusion DR KATE LANCASTER YORK PLASMA INSTITUTE In the beginning In the late fifties, alternative applications of nuclear explosions were being considered the number one suggestion
More informationInitial Experiments on the Shock-Ignition Inertial Confinement Fusion Concept
Initial Experiments on the Shock-Ignition Inertial Confinement Fusion Concept Introduction Shock ignition is a concept for direct-drive laser inertial confinement fusion (ICF) 1 3 that was recently proposed
More informationarxiv: v2 [physics.plasm-ph] 29 Dec 2016
Interplay of Laser-Plasma Interactions and Inertial Fusion Hydrodynamics D. J. Strozzi, D. S. Bailey, P. Michel, L. Divol, S. M. Sepke, G. D. Kerbel, C. A. Thomas, J. E. Ralph, J. D. Moody, M. B. Schneider
More informationIntegrated Modeling of Fast Ignition Experiments
Integrated Modeling of Fast Ignition Experiments Presented to: 9th International Fast Ignition Workshop Cambridge, MA November 3-5, 2006 R. P. J. Town AX-Division Lawrence Livermore National Laboratory
More informationLaser absorption, power transfer, and radiation symmetry during the first shock of ICF gas-filled hohlraum experiments
Laser absorption, power transfer, and radiation symmetry during the first shock of ICF gas-filled hohlraum experiments A. Pak, 1 E. L. Dewald, 1 O. L. Landen, 1 J. Milovich, 1 D. J. Strozzi, 1 L. F. Berzak
More informationFirst Results from Cryogenic-Target Implosions on OMEGA
First Results from Cryogenic-Target Implosions on OMEGA MIT 1 mm 1 mm 100 µm C. Stoeckl University of Rochester Laboratory for Laser Energetics 43rd Annual Meeting of the American Physical Society Division
More informationDual Nuclear Shock Burn:
Dual Nuclear Shock Burn: Experiment, Simulation, and the Guderley Model J.R. Rygg, J.A. Frenje, C.K. Li, F.H. Séguin, and R.D. Petrasso MIT PSFC J.A. Delettrez, V.Yu Glebov, D.D. Meyerhofer, and T.C. Sangster
More informationAdvanced Ignition Experiments on OMEGA
Advanced Ignition Experiments on OMEGA C. Stoeckl University of Rochester Laboratory for Laser Energetics 5th Annual Meeting of the American Physical Society Division of Plasma Physics Dallas, TX 17 21
More informationUsing multiple secondary fusion products to evaluate fuel ρr, electron temperature, and mix in deuterium-filled implosions at the NIF
Using multiple secondary fusion products to evaluate fuel ρr, electron temperature, and mix in deuterium-filled implosions at the NIF H. G. Rinderknecht, M. J. Rosenberg, A. B. Zylstra, B. Lahmann, F.
More informationFirst measurements of the absolute neutron spectrum using the Magnetic Recoil Spectrometer (MRS) at OMEGA (Invited) a)
PSFC/JA-08-21 First measurements of the absolute neutron spectrum using the Magnetic Recoil Spectrometer (MRS) at OMEGA (Invited) a) J.A. Frenje, D.T. Casey, C.K. Li, J.R. Rygg b), F.H. Seguin, R.D. Petrasso
More informationFirst-Principles Investigations on Ionization and Thermal Conductivity of Polystyrene (CH) for Inertial Confinement Fusion Applications
First-Principles Investigations on Ionization and Thermal Conductivity of Polystyrene (CH) for Inertial Confinement Fusion Applications Introduction Controlled inertial confinement fusion (ICF) has been
More informationProgress Toward Demonstration of Ignition Hydro-equivalence on OMEGA
Progress Toward Demonstration of Ignition Hydro-equivalence on OMEGA Hot-spot pressure (Gbar) 12 1 8 6 4 2 1 1-D LILAC calculations Convergence ratio Inferred from measurements 12 14 16 18 2 3-D ASTER
More informationAnalysis of Experimental Asymmetries using Uncertainty Quantification: Inertial Confinement Fusion (ICF) & its Applications
Analysis of Experimental Asymmetries using Uncertainty Quantification: Inertial Confinement Fusion (ICF) & its Applications Joshua Levin January 9, 2009 (Edited: June 15, 2009) 1 Contents 1. Uncertainty
More informationINVESTIGATION OF THE DEGENERACY EFFECT IN FAST IGNITION FOR HETEROGENEOUS FUEL
INVESTIGATION OF THE DEGENERACY EFFECT IN FAST IGNITION FOR HETEROGENEOUS FUEL M. MAHDAVI 1, B. KALEJI 1 Sciences Faculty, Department of Physics, University of Mazandaran P. O. Box 47415-416, Babolsar,
More informationThe National Ignition Facility: Transition to a User Facility
Journal of Physics: Conference Series PAPER OPEN ACCESS The National Ignition Facility: Transition to a User Facility To cite this article: E. I. Moses et al 2016 J. Phys.: Conf. Ser. 688 012073 View the
More informationProgress in Direct-Drive Inertial Confinement Fusion Research
Progress in Direct-Drive Inertial Confinement Fusion Research Ignition and Gain Total GtRH n (g/cm 2 ) 2 1.5.2.1 IAEA 21 DT, 22 kj IAEA 28 DT, 16 kj NIF.5 MJ NIF point design 1.5 MJ 1-D marginal ignition
More informationCapsule-areal-density asymmetries inferred from 14.7-MeV deuterium helium protons in direct-drive OMEGA implosions a
PHYSICS OF PLASMAS VOLUME 10, NUMBER 5 MAY 2003 Capsule-areal-density asymmetries inferred from 14.7-MeV deuterium helium protons in direct-drive OMEGA implosions a C. K. Li, b) F. H. Séguin, J. A. Frenje,
More informationNotes on fusion reactions and power balance of a thermonuclear plasma!
SA, 3/2017 Chapter 5 Notes on fusion reactions and power balance of a thermonuclear plasma! Stefano Atzeni See S. Atzeni and J. Meyer-ter-Vehn, The Physics of Inertial Fusion, Oxford University Press (2004,
More informationThe MIT Accelerator for development of ICF diagnostics at OMEGA / OMEGA-EP and the NIF
Introduction The MIT Accelerator for development of ICF diagnostics at OMEGA / OMEGA-EP and the NIF SBDs d + or 3 He +(2+) D or 3 He target Present MIT Graduate Students and the MIT Accelerator OLUG 21
More informationShock-Ignition Experiments on OMEGA at NIF-Relevant Intensities
Shock-Ignition Experiments on OMEGA at NIF-Relevant Intensities Shock ignition is a two-step inertial confinement fusion (ICF) concept in which a strong shock wave is launched at the end of the laser pulse
More informationCharles Cerjan. Nuclear Data Needs and Capabilities for Applications. Lawrence Berkeley National Laboratory. May 28, 2015
Charles Cerjan Nuclear Data Needs and Capabilities for Applications Lawrence Berkeley National Laboratory May 28, 2015 LLNL-PRES-670924 This work was performed under the auspices of the U.S. Department
More informationTime-Resolved Compression of a Spherical Shell with a Re-Entrant Cone to High Areal Density. for Fast-Ignition Laser Fusion
Time-Resolved Compression of a Spherical Shell with a Re-Entrant Cone to High Areal Density for Fast-Ignition Laser Fusion The compression of matter to a very high density is of general interest for high-energy-density
More informationThree-dimensional hydrodynamic simulations of OMEGA implosions
Three-dimensional hydrodynamic simulations of OMEGA implosions I. V. Igumenshchev, D. T. Michel Laboratory for Laser Energetics, University of Rochester 250 East River Road, Rochester, NY 14623, USA R.
More informationAnalysis of a Direct-Drive Ignition Capsule Design for the National Ignition Facility
Analysis of a Direct-Drive Ignition Capsule Design for the National Ignition Facility R (mm) 1 8 6 4 End of acceleration phase r(g/cc) 7.5 3.5.5 Gain 4 3 2 1 1 2 2 s (mm) 5 25 25 5 Z (mm) P. W. McKenty
More informationThe Effect of Laser Spot Shapes on Polar-Direct-Drive Implosions on the National. Ignition Facility. 250 East River Road, Rochester, NY 14623
The Effect of Laser Spot Shapes on Polar-Direct-Drive Implosions on the National Ignition Facility F. Weilacher, 1,2 P. B. Radha, 1,* T. J. B. Collins, 1 and J. A. Marozas 1 1 Laboratory for Laser Energetics,
More informationExperimental Demonstration of X-Ray Drive Enhancement with Rugby-Shaped Hohlraums
Experimental Demonstration of X-Ray Drive Enhancement with Rugby-Shaped Hohlraums The MIT Faculty has made this article openly available. Please share how this access benefits you. Your story matters.
More informationX-ray driven implosions at ignition relevant velocities on the National Ignition Facilitya) Phys. Plasmas 20, (2013); /1.
A Particle X-ray Temporal Diagnostic (PXTD) for studies of kinetic, multi-ion effects, and ion-electron equilibration rates in Inertial Confinement Fusion plasmas at OMEGA (invited) H. Sio, J. A. Frenje,
More informationNew developments in the theory of ICF targets, and fast ignition with heavy ions
INSTITUTE OF PHYSICS PUBLISHING Plasma Phys. Control. Fusion 45 (2003) A125 A132 PLASMA PHYSICS AND CONTROLLED FUSION PII: S0741-3335(03)68658-6 New developments in the theory of ICF targets, and fast
More informationA Neutron Temporal Diagnostic for High-Yield DT Cryogenic Implosions on OMEGA
A Neutron Temporal Diagnostic for High-Yield DT Cryogenic Implosions on Introduction The temporal history of the neutron production in inertial confinement fusion (ICF) experiments 1 is an important diagnostic
More informationEffects of Atomic Mixing in Inertial Confinement Fusion by Multifluid Interpenetration Mix Model
Commun. Theor. Phys. (Beijing, China) 52 (2009) pp. 1102 1106 c Chinese Physical Society and IOP Publishing Ltd Vol. 52, No. 6, December 15, 2009 Effects of Atomic Mixing in Inertial Confinement Fusion
More informationMonoenergetic proton backlighter for measuring E and B fields and for radiographing implosions and high-energy density plasmas invited
REVIEW OF SCIENTIFIC INSTRUMENTS 77, 10E725 2006 Monoenergetic proton backlighter for measuring E and B fields and for radiographing implosions and high-energy density plasmas invited C. K. Li, a F. H.
More informationD- 3 He Protons as a Diagnostic for Target ρr
D- 3 He Protons as a Diagnostic for Target ρr Areal density (ρr) is an important parameter for measuring compression in ICF experiments. Several diagnostics employing nuclear particles have been considered
More informationMeasured dependence of nuclear burn region size on implosion parameters in inertial confinement fusion experiments
PSFC/JA-6-1 Measured dependence of nuclear burn region size on implosion parameters in inertial confinement fusion experiments F. H. Séguin, 1 J. L. DeCiantis, 1 J. A. Frenje, 1 C. K. Li, 1 J. R. Rygg,
More informationIgnition and Burn in a Small Magnetized Fuel Target
Ignition and Burn in a Small Magnetized Fuel Target Ronald C. Kirkpatrick, Los Alamos National Laboratory, Los Alamos, NM, USA E-mail: rck@lanl.gov Abstract LASNEX calculations of a small magnetized target
More informationDirect-Drive, High-Convergence-Ratio Implosion Studies on the OMEGA Laser System
Direct-Drive, High-Convergence-Ratio Implosion Studies on the OMEGA Laser System F. J. Marshall, J. A. Delettrez, R. Epstein, V. Yu. Glebov, D. D. Meyerhofer, R. D. Petrasso,P.B.Radha,V.A.Smalyuk,J.M.Soures,C.Stoekl,R.P.J.Town,
More informationDirect-drive fuel-assembly experiments with gas-filled, cone-in-shell, fast-ignitor targets on the OMEGA Laser
INSTITUTE OF PHYSICS PUBLISHING Plasma Phys. Control. Fusion 47 (25) B859 B867 PLASMA PHYSICS AND CONTROLLED FUSION doi:1.188/741-3335/47/12b/s68 Direct-drive fuel-assembly experiments with gas-filled,
More informationImproved target stability using picket pulses to increase and shape the ablator adiabat a
PHYSICS OF PLASMAS 12, 056306 2005 Improved target stability using picket pulses to increase and shape the ablator adiabat a J. P. Knauer, b K. Anderson, R. Betti, T. J. B. Collins, V. N. Goncharov, P.
More informationThree-Dimensional Studies of the Effect of Residual Kinetic Energy on Yield Degradation
Threeimensional Studies of the Effect of Residual Kinetic Energy on Yield Degradation Kinetic energy density for single-mode, = 1, m = 6 1. YOC model = (1 RKE) 4.4 1 3 to ( Jm / ) 5.797 1 15 1.44 1 1 z
More informationImproving hot-spot pressure for ignition in high-adiabat inertial confinement fusion implosion
Improving hot-spot preure for ignition in high-adiabat inertial confinement fusion implosion Dongguo Kang( 康洞国 ),* Shaoping Zhu( 朱少平 ), Wenbing Pei( 裴文兵 ), Shiyang Zou( 邹士阳 ), Wudi Zheng( 郑无敌 ), Jianfa
More informationNational direct-drive program on OMEGA and the National Ignition Facility
Plasma Physics and Controlled Fusion PAPER National direct-drive program on OMEGA and the National Ignition Facility To cite this article: V N Goncharov et al Plasma Phys. Control. Fusion 00 Manuscript
More informationD 3 He proton spectra for diagnosing shell R and fuel T i of imploded capsules at OMEGA
PHYSICS OF PLASMAS VOLUME 7, NUMBER 6 JUNE 2000 D 3 He proton spectra for diagnosing shell R and fuel T i of imploded capsules at OMEGA C. K. Li, D. G. Hicks, F. H. Séguin, J. A. Frenje, and R. D. Petrasso
More informationAreal-Density-Growth Measurements with Proton Spectroscopy on OMEGA
Areal-Density-Growth Measurements with Proton Spectroscopy on OMEGA Areal density (mg/cm ) 5 15 1 5 4 atm D 3 He 1.6 1... 1 1 1 1 19 1 1 Neutron rate (s 1 ) V. A. Smalyuk Laboratory for Laser Energetics
More informationJournal of Physics: Conference Series PAPER OPEN ACCESS. To cite this article: T J Murphy et al 2016 J. Phys.: Conf. Ser.
Journal of Physics: Conference Series PAPER OPEN ACCESS Progress in the development of the MARBLE platform for studying thermonuclear burn in the presence of heterogeneous mix on OMEGA and the National
More informationThe T(t, 2n)α, T( 3 He, np)α, and 3 He( 3 He, 2p)α Reactions at Low Energies
The T(t, 2n)α, T( 3 He, np)α, and 3 He( 3 He, 2p)α Reactions at Low Energies Carl R. Brune Ohio University 5 March 2015 INT Workshop INT 15-58W: Reactions and Structure of Exotic Nuclei Overview of Presentation
More informationA Multi-Dimensional View of the US Inertial Confinement Fusion Program
Photos placed in horizontal position with even amount of white space between photos and header To replace these boxes with images open the slide master A Multi-Dimensional View of the US Inertial Confinement
More informationMeasurements of hohlraum-produced fast ions
Measurements of hohlraum-produced fast ions A. B. Zylstra, C. K. Li, F. H. Séguin, M. J. Rosenberg, H. G. Rinderknecht et al. Citation: Phys. Plasmas 19, 042707 (2012); doi: 10.1063/1.4707410 View online:
More informationProton Temporal Diagnostic for ICF Experiments on OMEGA
Proton Temporal Diagnostic for ICF Experiments on OMEGA Introduction In an inertial confinement fusion (ICF) 1 experiment, a capsule filled with deuterium (D 2 ) or a deuterium tritium (DT) fuel is heated
More informationMeasurements of Stellar and Big-Bang Nucleosynthesis Reactions Using Inertially-Confined Plasmas
Measurements of Stellar and Big-Bang Nucleosynthesis Reactions Using Inertially-Confined Plasmas Alex Zylstra INPC 2016 Adelaide, Australia Sep. 12-16, 2016 LA-UR-16-26746 Operated by Los Alamos National
More informationT.J. M Urphy, P-24. K.A. Klare, P-24
\ LA-UR- 96 *- c o d F -. q f Q o b ao&--. Title: Author@): Submitted to: NEUTRON TME-OF-FLGHTFROM EXPANDNG OR CONTRACTNGSPHERCAL SOURCES. Q T.J. M Urphy, P-4 R.E. Chrien, P-4 K.A. Klare, P-4 1lth High
More informationThe National Direct-Drive Program
The National Direct-Drive Program Ignition hydro-equivalence on OMEGA 1.8 MJ 26 kj Verify laser plasma interaction scaling at the National Ignition Facility T. C. Sangster University of Rochester Laboratory
More informationIgnition Regime and Burn Dynamics of D T-Seeded D 3 He Fuel for Fast Ignition Inertial Confinement Fusion
Ignition Regime and Burn Dynamics of D T-Seeded D 3 He Fuel for Fast Ignition Inertial Confinement Fusion Y. Nakao, K. Tsukida, K. Shinkoda, Y. Saito Department of Applied Quantum Physics and Nuclear Engineering,
More informationMIT Research using High-Energy Density Plasmas at OMEGA and the NIF
MIT Research using High-Energy Density Plasmas at OMEGA and the NIF 860 μm 2.3 μm SiO 2 D 3 He gas 1 10 11 D-D 3 He D-D T Yield D-D p D- 3 He 0 0 5 10 15 Energy (MeV) D- 3 He p Hans Rinderknecht Wednesday,
More informationBulk Fluid Velocity Construction from NIF Neutron Spectral Diagnostics
Bulk Fluid elocity Construction from NIF Neutron Spectral Diagnostics ntof-4.5 DT-Lo (64-309) ntof-3.9 DSF (64-275) ntof-4.5 BT (64-253) MRS ntof-4.5 DT-Hi (64-330) Spec E (90-174) Spec A (116-316) Spec
More informationPolar-Drive Implosions on OMEGA and the National Ignition Facility
Polar-Drive Implosions on OMEGA and the National Ignition Facility Introduction Polar drive (PD) 1 provides the capability to perform directdrive ignition experiments on laser facilities like the National
More informationarxiv: v1 [physics.plasm-ph] 27 Oct 2017
Radiation dominated implosion with nano-plasmonics Radiation dominated implosion with nano-plasmonics L. P. Csernai, 1, 2, a) N. Kroo, 3 and I. Papp 2, 4 1) Dept. of Physics and Technology, Univ. of Bergen,
More informationHydrodynamics of Exploding Foil X-Ray Lasers with Time-Dependent Ionization Effect
Hydrodynamics of Exploding Foil X-Ray Lasers with Time-Dependent Ionization Effect WANG Yu ( ), SU Dandan ( ), LI Yingjun ( ) State Key Laboratory for GeoMechanics and Deep Underground Engineering, China
More information