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Journal articles on the topic 'Pellet fusion'

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Published: 4 June 2021

Last updated: 20 February 2023

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1

Kasotakis, G., L. Cicchitelli, H. Hora, and R. J. Stening. "Volume ignition in pellet fusion." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 278, no. 1 (May 1989): 110–13. http://dx.doi.org/10.1016/0168-9002(89)91143-1.

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2

Yuan, Shaohua, Nizar Naitlho, Roman Samulyak, Bernard Pégourié, Eric Nardon, Eric Hollmann, Paul Parks, and Michael Lehnen. "Lagrangian particle simulation of hydrogen pellets and SPI into runaway electron beam in ITER." Physics of Plasmas 29, no. 10 (October 2022): 103903. http://dx.doi.org/10.1063/5.0110388.

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Numerical studies of the ablation of pellets and shattered pellet injection (SPI) fragments into a runaway electron beam in ITER have been performed using a time-dependent pellet ablation code [Samulyak et al., Nucl. Fusion, 61(4), 046007 (2021)]. The code resolves detailed ablation physics near pellet fragments and large-scale expansion of ablated clouds. The study of a single-fragment ablation quantifies the influence of various factors, in particular, the impact ionization by runaway electrons and cross-field transport models, on the dynamics of ablated plasma and its penetration into the runaway beam. Simulations of SPI performed using different numbers of pellet fragments study the formation and evolution of the ablation clouds and their large-scale dynamics in ITER. The penetration depth of the ablation clouds is found to be of the order of 50 cm.

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3

Wang, Zhehui, M. A. Hoffbauer, E. M. Hollmann, Z. Sun, Y. M. Wang, N. W. Eidietis, Jiansheng Hu, R. Maingi, J. E. Menard, and X. Q. Xu. "Hollow pellet injection for magnetic fusion." Nuclear Fusion 59, no. 8 (June 27, 2019): 086024. http://dx.doi.org/10.1088/1741-4326/ab19eb.

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4

Beller, Denis E., John M. Jacobson, George H. Miley, Maria Petra, and Yasser Shaban. "Parametric design study of a nuclear-pumped laser-driven inertial confinement fusion power plant." Laser and Particle Beams 11, no. 3 (September 1993): 537–48. http://dx.doi.org/10.1017/s026303460000519x.

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In an earlier preliminary design study, we proposed a novel nuclear-pumped laser-driven (NPL) inertial confinement fusion (ICF) power reactor that represents an important variation on the “neutron feedback” concept for ICF. This NPL-driven ICF concept also included an advanced, DT-seeded, D3He-fueled pellet and magnetic protection of the first wall of the reactor chamber. Advantages that were demonstrated for this approach included increased efficiency for laser-to-target energy coupling, increased efficiency for thermalto-electric energy conversion, and reduced neutron activation and waste. The coupling efficiency is enhanced because a nuclear-pumped flashlamp is directly pumped by fission fragments from uranium micropellets within the lamp medium. The thermal conversion efficiency is greater because a large fraction of the ICF pellet&s fusion yield is in charged Finally, the fraction of the fusion yield carried by neutrons is significantly reduced in comparison with pure D-T-fueled pellets; thus, neutron-induced activity in the first wall is decreased and safety is increased. The initial study indicated these factors could result in a required driver energy of 5 MJ (vice 10 MJ currently projected) and a pellet gain of only 50 (vice 100 currently projected) for a feasible l,000-MWe power reactor operating with approximately six pellets per second. The current study includes a refined analysis of an NPL-driven ICF power reactor of this type. A cylindrical design for the fission/NPL blanket is selected as a “natural” geometry for pumping the NPL. Required enrichments and criticalities are then predicted for the multiplication of the fusion neutron yield needed to pump the NPL. Based upon these results, we report a more detailed parametric study of the efficiencies for converting neutron, X-ray, and plasma yields from advanced ICF pellets into electrical and optical energy flows required in this concept. We also examined breeding tritium in a lithium blanket layer. Results from these studies help define topics and parameter spaces for further research on this unique reactor concept.

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5

Mori, Y., K. Ishii, R. Hanayama, S. Okihara, Y. Kitagawa, Y. Nishimura, O. Komeda, et al. "Ten hertz bead pellet injection and laser engagement." Nuclear Fusion 62, no. 3 (February 3, 2022): 036028. http://dx.doi.org/10.1088/1741-4326/ac3d69.

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Abstract A laser inertial fusion energy (IFE) reactor requires repetitive injection of fuel pellets and laser engagement to fuse fusion fuel beyond a few Hz. We demonstrate 10 Hz free-fall bead pellet injection and laser engagement with γ-ray generation. Deuterated polystyrene beads with a diameter of 1 mm were engaged by counter illuminating ultra-intense laser pulses with an intensity of 5 × 1017 W cm−2 at 10 Hz. The spatial distribution of free-fall beads was 0.86 mm in the horizontal direction and 0.18 mm in the vertical direction. The system operated for more than 5 min and 3500 beads were supplied with achieved frequencies of 2.1 Hz for illumination on the beads and 0.7 Hz for γ-ray generation; these frequencies were three times greater than with the previous 1 Hz injection system. The duration of operation was limited by the pellet supply. This injection and engagement system could be used for laser IFE research platforms.

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6

Yoshida, H., K. Katakami, Y. Sakagami, H. Azechi, H. Nakarai, and S. Nakai. "Magnetic suspension of a pellet for inertial confinement fusion." Laser and Particle Beams 11, no. 2 (June 1993): 455–59. http://dx.doi.org/10.1017/s0263034600005048.

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In inertial confinement fusion experiments, the symmetrical implosion calls for a new scheme: a nonsupported pellet. In this article, the first experiment is conducted using a plastic pellet covered with thin ferromagnetic material. In the system, the digital-phase-lead-compensator takes the position-related signal and processes it to provide a driving signal for the magnetic suspender. The suspended pellet is irradiated by the Gekko XII laser, having its total energy 2700 J with pulse width 800 ps at the wavelength 0.53 μm. The X-ray pinhole photograph confirms the spherically symmetrical implosion at the pellet core. At irradiation, the neutron yield is also observed.

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7

Nakai, S. "Pellet and implosion scaling." Laser and Particle Beams 7, no. 4 (November 1989): 711–20. http://dx.doi.org/10.1017/s0263034600006182.

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Recent progress of pellet implosion research is remarkable in the obtainment of a high density (100 times solid density) and a high temperature plasma (which produces thermonuclear neutrons of 1013 per shot or a pellet gain of 0·2%) and in the corresponding understanding of the implosion physics. The data bases for laser fusion have been accumulated in preparation for a fusion ignition experiment and the achievement of break-even condition, which is estimated to be possible with 100 kJ blue laser.The recent progress of driver technology, such as new types of solid state lasers, excimer laser, light ion beam (LIB), heavy ion beam (HIB) and free electron laser, now enabled us to design a high pellet gain experiment with a MJ driver.

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8

Nakashima, H., M. Shinohara, Y. Wakuta, T. Honda, Y. Nakao, and H. Takabe. "Numerical simulation of implosion and burn of D–T ignitor/D3He fuel pellet for D3He inertial confinement fusion reactor." Laser and Particle Beams 11, no. 1 (March 1993): 137–47. http://dx.doi.org/10.1017/s0263034600006996.

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A parameter study of implosion, burn, and gain of D–T ignitor/D3He fuel pellets is presented for a D3He inertial confinement fusion reactor. It is found from burn simulation that attaining a quasi-isobaric state with a temperature of 4 keV and pR value of 2.5 g/cm2 for the D–T ignitor and 0.8 keV and 9.5 g/cm2 for the D3He main fuel would suffice to obtain a pellet gain of ∼40–50 required for the D3He reactor. With 30-MJ laser irradiation and the coupling efficiency of 10%, the density of the target is assumed to be imploded to 5,000 times the liquid density. However, in the implosion simulation to realize the above configuration it is found that after void closure the central hot D–T ignitor region is ignited, while the bulk of the D3He main fuel is still imploding with high velocities. This preignition of the D–T ignitor leads to a low compression of the main fuel and prevents the D–T/D3He pellet from obtaining the required pellet gain. The pellet gain obtained is only ∼3.

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9

Kawata, Shigeo. "Inhomogeneous mixing of D and T fuels in inertial confinement fusion." Laser and Particle Beams 13, no. 3 (September 1995): 383–88. http://dx.doi.org/10.1017/s0263034600009514.

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Numerical analyses show that a 40% mixing inhomogeneity of the deuterium (D) and tritium (T) concentrations in a DT pellet still gives a sufficient fusion energy output in DT inertial confinement fusion (ICF), as long as the D and T total amounts are equal. This new result means that fusion energy output is rather insensitive to the inhomogeneous fuel mixing in the DT ICF pellet.

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10

MAHDAVI, M., and B. JALALY. "EFFECTS OF DEUTERIUM–LITHIUM FUSION REACTION ON INTERNAL TRITIUM BREEDING." International Journal of Modern Physics E 19, no. 11 (November 2010): 2123–32. http://dx.doi.org/10.1142/s0218301310016545.

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The optimal usage of designed fuel pellets is one of the very important parameters in inertial confinement fusion (ICF) systems. In this research, time-dependent dynamical equations for D/D fuel are written by considering impurity of 6 Li . Then dependency of gain on temperature, density and pellet radius is studied using Runge–Kutta method. The obtained results show that the energy gain will be maximized at the initial temperature 35 keV, density, 5000 g/cm3 and ratio impurity of 6 Li , 0.05.

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11

NAKAI, Sadao, Kunioki MIMA, Takayoshi NORIMATSU, and Masaru TAKAGI. "Present Status of Laser Fusion Fuel Pellet." Review of Laser Engineering 14, no. 12 (1986): 1045–65. http://dx.doi.org/10.2184/lsj.14.1045.

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12

Kuteev, B. V. "Pellet-injection-based technologies for fusion reactors." Technical Physics 44, no. 9 (September 1999): 1058–62. http://dx.doi.org/10.1134/1.1259470.

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13

MULSER, P., and D. BAUER. "Fast ignition of fusion pellets with superintense lasers: Concepts, problems, and prospectives." Laser and Particle Beams 22, no. 1 (March 2004): 5–12. http://dx.doi.org/10.1017/s0263034604221024.

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The concept of fast ignition of precompressed pellets for inertial confinement fusion is presented and the main approaches are discussed. Numerical simulations of fast coronal ignition and the peculiarities of this scheme are considered in detail. Particular attention is devoted to the energy transport in the pellet corona. It is shown that fast coronal ignition will be successful only if the energy deposition by the fast electrons is anomalous over a sufficiently extended overdense region. Alternative schemes are briefly discussed.

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14

Tabaru, Y., Y. Nakao, H. Nakashima, and K. Kudo. "Areal density diagnostics using suprathermal fusion reaction for laser-imploded D-T pellets." Laser and Particle Beams 16, no. 1 (March 1998): 153–76. http://dx.doi.org/10.1017/s0263034600011848.

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Detecting highly energetic neutrons produced by suprathermal fusion reactions is expected as a useful method for the areal density diagnosis in future ICF experiments. This paper examines the possibility of ρR diagnosis using suprathermal fusions, on the basis of transport calculations for neutrons and charged particles. Not only neutron elastic scattering but also nuclear elastic scattering of α-particles are considered as the processes producing energetic recoil ions. Since the suprathermal fusion reaction is affected by the plasma temperature through the slowing-down process of energetic α-particles and recoil ions, the yield ratio of highly energetic neutrons emitted from suprathermal fusions to total ones depends considerably on tne temperature. An areal density diagnostic method based on neutron spectroscopy is proposed here that can eliminate the influence of the plasma temperature on the determination of the areal density. Moreover, on the basis of coupled transport/hydrodynamic calculation, we derive a more realistic energy spectrum of neutrons escaping from laser-imploded D-T pellet and examine the usefulness of the diagnosis method proposed in this paper. It is shown that the Method proposed here may be useful for the areal density diagnosis in the ignition-grade ICF Pellets.

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15

Andelfinger, C., E. Buchelt, P. Cierpka, H. Kollotzek, P. T. Lang, R. S. Lang, G. Prausner, F. X. Söldner, M. Ulrich, and G. Weber. "A new centrifuge pellet injector for fusion experiments." Review of Scientific Instruments 64, no. 4 (April 1993): 983–89. http://dx.doi.org/10.1063/1.1144101.

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16

Onozuka, Masanori, Yasushi Oda, Kingo Azuma, Kouji Satake, Satoshi Kasai, and Kouichi Hasegawa. "Railgun pellet injection system for fusion experimental devices." Fusion Engineering and Design 30, no. 4 (November 1995): 373–83. http://dx.doi.org/10.1016/0920-3796(95)00415-h.

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17

TABARU, Yasuhiko, Yasuyuki NAKAO, Hideki NAKASHIMA, and Kazuhiko KUDO. "Suprathermal Fusion Reactions in Laser-imploded DT Pellet and Its Applicability to Pellet Diagnosis." Journal of Nuclear Science and Technology 32, no. 8 (August 1995): 813–15. http://dx.doi.org/10.1080/18811248.1995.9731777.

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18

Daley, Patrick James, Orla Williams, Cheng Heng Pang, Tao Wu, and Edward Lester. "The impact of ash pellet characteristics and pellet processing parameters on ash fusion behaviour." Fuel 251 (September 2019): 779–88. http://dx.doi.org/10.1016/j.fuel.2019.03.142.

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19

Rubbia, Carlo. "Heavy-ion accelerators for inertial confinement fusion." Laser and Particle Beams 11, no. 2 (June 1993): 391–414. http://dx.doi.org/10.1017/s0263034600004985.

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Two concepts have been applied to the classical problem of accelerators for the ignition of indirectly driven inertial fusion. The first is the use of non-Liouvillian stacking based on photoionisation of a singly charged ion beam. A special FEL appears the most suited device to generate the appropriate light beam intensity at the required wavelength. The second is based on the use of a large number of (>1000) beamlets–or “beam straws”–all focussed by an appropriate magnetic structure and concentrated on the same spot on the pellet. The use of a large number of beams–each with a relatively low-current density–elegantly circumvents the problems of space charge, making use of the non-Liouvillian nature of the stopping power of the material of the pellet. The present conceptual design is based on a low-current (〈i〉 ≈ 50 mA) heavy-ion beam accelerated with a standard LINAC structure and accumulated in a stack of rings with the help of photoionisation. Beams are then extracted simultaneously from all the rings and further subdivided with the help of a switchyard of alternate paths separating and synchronising the many bunches from each ring before they hit the pellet. Single beam straws carry a reasonable number of ions: Beams and technology are directly relatable to the ones presently employed, for instance, at the CERN-PS. Space-charge-dominated conditions arise only during the last few turns before extraction and in the beam transport channel to the reaction chamber. In a practical example, we aim at a peak power of 500 TW delivered to the pellet for a duration of 10–15 ns. High-energy (10 GeV) beam straws of Ba doubly ionised ions are concentrated on several (four) focal spots of a radius of about 1 mm. The power density deposited on these tiny cylindrical absorbers inside a hermetic “hohlraum” is about 2.5 × 1016 w/g. These conditions are believed to be optimal for X-ray conversion, i.e., with an estimated conversion efficiency of about 90%.

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20

Nakai, S. "Laser fusion experiment." Laser and Particle Beams 7, no. 3 (August 1989): 467–75. http://dx.doi.org/10.1017/s0263034600007424.

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The recent progress of laser fusion research has been remarkable in obtaining the high density of more than 100 times solid density (Nakai et al. 1988) and high temperature plasma producing thermonuclear neutrons of 1013 per shot (pellet gain of 0·2%) (Yamanaka et al. 1986a) and in the understanding of the implosion physics. The data bases of the laser fusion are rapidly being accumulated and the technologies for the advanced experiments have been developed, both of which enable us to proceed toward the fusion ignition experiment and the achievement of the breakeven conditions.

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21

BRET, ANTOINE, and CLAUDE DEUTSCH. "Density gradient effects on beam plasma linear instabilities for fast ignition scenario." Laser and Particle Beams 24, no. 2 (June 2006): 269–73. http://dx.doi.org/10.1017/s0263034606060411.

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In the fast ignition scenario for inertial fusion, a relativistic electron beam is supposed to travel from the side of the fusion pellet to its core. One one hand, a relativistic electron beam passing through a plasma is a highly unstable system. On the other hand, the pellet core is denser than its side by four orders of magnitude so that the beam makes its way through a important density gradient. We here investigate the effect of this gradient on the instabilities. It is found that they should develop so early that gradient effects are negligible in the linear phase.

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22

NORIMATSU, Takayoshi, and Yukio SAKAGAMI. "Special issue on laser fusion and precision engineering. Micromachining for laser fusion pellet." Journal of the Japan Society for Precision Engineering 55, no. 11 (1989): 1944–47. http://dx.doi.org/10.2493/jjspe.55.1944.

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23

Contreras-Trejo, Juan Carlos, Daniel José Vega-Nieva, Maginot Ngangyo Heya, José Angel Prieto-Ruíz, Cynthya Adriana Nava-Berúmen, and Artemio Carrillo-Parra. "Sintering and Fusibility Risks of Pellet Ash from Different Sources at Different Combustion Temperatures." Energies 15, no. 14 (July 9, 2022): 5026. http://dx.doi.org/10.3390/en15145026.

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Pellets are solid biofuels with a combustion efficiency of 85–90%, low CO2 emissions and costs, great comfort and versatility. However, the ash generated during combustion can present sintering and fusibility, decreasing boiler efficiency and potentially malfunctioning. Ash composition indexes can be useful to predict observed ash sintering and fusion but require further analysis for a variety of feedstocks. The objective of this work was to determine the effect of the mineral composition of pellet ash from 15 biomasses of forest and agro-industrial sources on observed pellet ash slagging using a laboratory test. The chemical composition of pellets and the indexes B, NaK/B, SiP/CaMg and SiPNaK/CaMg at 550 and 1000 °C were determined. Pearson correlation tests were also performed between cumulative percentages of slag at different sieve sizes. The concentrations of CaO ranged from 4.49 to 65.95%, MgO varied from 1.99 to 17.61%, and the SiO2 concentration was between 16.11 and 28.24% and 2.19–56.75% at 550 and 1000 °C, respectively. Pellets of forest origin presented a low risk of slag formation, while those from agro-industrial sources showed a high risk of slag formation. The index SiPNaK/CaMg showed the highest correlation (R2 > 0.75) to observed slagging using the BioSlag test.

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24

Kubo, Takeaki, Takahiro Karino, Hiroki Kato, and Shigeo Kawata. "Fuel Pellet Alignment in Heavy-Ion Inertial Fusion Reactor." IEEE Transactions on Plasma Science 47, no. 1 (January 2019): 2–8. http://dx.doi.org/10.1109/tps.2018.2876471.

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25

Csernai, L. P., and D. D. Strottman. "Volume ignition via time-like detonation in pellet fusion." Laser and Particle Beams 33, no. 2 (April 10, 2015): 279–82. http://dx.doi.org/10.1017/s0263034615000397.

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AbstractRelativistic fluid dynamics and the theory of relativistic detonation fronts are used to estimate the space–time dynamics of the burning of the Deuterium–Tritium fuel in laser-driven pellet fusion experiments. The initial “High foot” heating of the fuel makes the compressed target transparent to radiation, and then a rapid ignition pulse can penetrate and heat up the whole target to supercritical temperatures in a short time, so that most of the interior of the target ignites almost simultaneously and instabilities will have no time to develop. In these relativistic, radiation-dominated processes both the interior, time-like burning front, and the surrounding space-like part of the front will be stable against Rayleigh–Taylor instabilities. To achieve this rapid, volume ignition the pulse heating up the target to supercritical temperature should provide the required energy in less than 10 ps.

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26

Li, Jie, Liyan Zhang, Yang Wang, Fei Li, Daliang Li, and Yang Han. "Deep Fusion Feature Extraction and Classification of Pellet Phase." IEEE Access 8 (2020): 75428–36. http://dx.doi.org/10.1109/access.2020.2988831.

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27

Lengyel, L. L., and K. Borrass. "Fueling of Fusion Reactors By Means of Pellet Injection." Fusion Technology 8, no. 1P2B (July 1985): 1760–65. http://dx.doi.org/10.13182/fst85-a40015.

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28

Nakamura, H., T. Kubo, T. Karino, H. Kato, and S. Kawata. "Fuel pellet injection into heavy-ion inertial fusion reactor." High Energy Density Physics 35 (June 2020): 100741. http://dx.doi.org/10.1016/j.hedp.2019.100741.

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29

Yamanaka, C. "Present and future of laser fusion." Laser and Particle Beams 7, no. 3 (August 1989): 477–82. http://dx.doi.org/10.1017/s0263034600007436.

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The key issues of laser fusion are to achieve highly efficient implosion by the ablation and to reach the high gain of a fuel pellet. Measures of the success are the neutron yield and the areal density of the fuel. Recent results show the neutron yield per laser shot to be 1013, and the ρR is 0·2g/cm2. These data seem to be approaching the breakeven condition.

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30

Kawata, Shigeo, and Hideki Nakashima. "Tritium content of a DT pellet in inertial confinement fusion." Laser and Particle Beams 10, no. 3 (September 1992): 479–84. http://dx.doi.org/10.1017/s0263034600006728.

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A numerical and analytical estimation and a one-dimensionalhydrodynamic simulation show that a 30%reduction of the tritium content in a D-T pellet still gives sufficient energy output in aD-T inertial confinement fusion reactor.In other words, the tritiumb content can be reduced significantly without a significant reduction in the D-T fusion energy output.This new result also meansthat the tritium inventory can be reduced significantly before and during the reactor operation in the D-T inertial confinement fusion.This result comes from the contribution of a D-D reaction to the D-T reaction.

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31

MAHDAVI, M., and T. KOOHROKHI. "ENERGY LEAKAGE PROBABILITY EFFECT ON IGNITION CONDITION IN AN INERTIAL CONFINEMENT FUSION PLASMA." International Journal of Modern Physics B 25, no. 27 (October 30, 2011): 3611–22. http://dx.doi.org/10.1142/s0217979211101983.

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For a weak to moderately coupled plasma, the charged particle stopping power dE/dx was recently calculated from first principles in Ref. 1 using the method of dimensional continuation.2 While the calculational techniques were imported from quantum field theory, the calculation itself lies squarely within the standard framework of convergent kinetic equations. By using these calculations, ignition condition regime in (D/Tx/3Hey) fusion fuel pellet is investigated, including energy deposition fraction of charged particles and neutrons in fuel pellet, bremsstrahlung and inverse bremsstrahlung radiation, inverse Compton scattering and thermal conduction losses.

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32

Mahdavi, M., T. Koohrokhi, and Z. Barfami. "The Effect of Energy Leakage Probability on Burn Propagation in an Optically Thick Fusion Plasma." ISRN High Energy Physics 2012 (2012): 1–10. http://dx.doi.org/10.5402/2012/838394.

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In an optically thick plasma, the mean free path of bremsstrahlung photons is smaller than the plasma radius, and radiation can be treated as a photon gas in thermal equilibrium. In these conditions, the black body radiation spectrum exceeds the number of hot photons, and reabsorption processes such as inverse bremsstrahlung radiation and inverse Compton scattering become important. It has been shown that a dense fusion plasma like the one being used in ICF method is initially optically thick. When the fuel pellet is burning, the temperature of its electrons rises (approximately greater than 90 KeV), and the pellet becomes rapidly optically thin. In this paper, we have shown that the energy leakage probability makes electron temperature remain low (approximately smaller than 55 KeV), and as a result the fuel pellet remains optically thick during burning.

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33

Evans, R. G. "The basic physics of laser fusion." Canadian Journal of Physics 64, no. 8 (August 1, 1986): 893–99. http://dx.doi.org/10.1139/p86-158.

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The essential features of a laser-fusion pellet are shown to be a high-density, high-pressure core with a central hot spot. The pressure in this core is produced by amplification of the laser ablation pressure during the spherical implosion. A high degree of symmetry in the implosion is required and the related subjects of symmetry and hydrodynamic stability are briefly discussed. The laser–plasma interaction process is important in producing high-absorption efficiency without preheating the core by fast electrons.

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34

YOSHIDA, Hiroki, Shinya YAMADORI, and Yukio SAKAGAMI. "Accurate Metal Thickness Determination of a Pellet for Laser Fusion." Review of Laser Engineering 26, no. 3 (1998): 268–71. http://dx.doi.org/10.2184/lsj.26.268.

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35

Budny, R. V. "Comment on Li pellet conditioning in tokamak fusion test reactor." Physics of Plasmas 18, no. 9 (September 2011): 092506. http://dx.doi.org/10.1063/1.3626541.

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36

Houlberg, W. A., S. E. Attenberger, and M. J. Grapperhaus. "Density profile control in a fusion reactor using pellet injection." Nuclear Fusion 34, no. 1 (January 1994): 93–108. http://dx.doi.org/10.1088/0029-5515/34/1/i07.

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37

Yoshida, H., K. Hirose, and Y. Sakagami. "Active damper of magnetically suspended pellet for laser fusion scheme." Fusion Engineering and Design 44, no. 1-4 (February 1999): 467–70. http://dx.doi.org/10.1016/s0920-3796(98)00371-8.

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38

Parks, P. B., J. S. Leffler, and R. K. Fisher. "Analysis of low Zaimpurity pellet ablation for fusion diagnostic studies." Nuclear Fusion 28, no. 3 (March 1, 1988): 477–90. http://dx.doi.org/10.1088/0029-5515/28/3/012.

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39

Ogoyski, A. I., S. Kawata, T. Someya, A. B. Blagoev, and P. H. Popov. "32-Beam irradiation on a spherical heavy ion fusion pellet." Journal of Physics D: Applied Physics 37, no. 17 (August 20, 2004): 2392–94. http://dx.doi.org/10.1088/0022-3727/37/17/008.

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40

Kreutz, Ronald. "Pellet Delivery for the Conceptual Inertial Confinement Fusion Reactor Hiball." Fusion Technology 8, no. 3 (November 1985): 2708–20. http://dx.doi.org/10.13182/fst85-a24692.

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41

Kawata, S., T. Sato, T. Teramoto, E. Bandoh, Y. Masubichi, and I. Takahashi. "Radiation effect on pellet implosion and Rayleigh-Taylor instability in light-ion beam inertial confinement fusion." Laser and Particle Beams 11, no. 4 (December 1993): 757–68. http://dx.doi.org/10.1017/s0263034600006492.

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The radiation transport effect on pellet implosion and the Rayleigh-Taylor (R-T) instability are studied in a light-ion beam (LIB) inertial confinement fusion (ICF) by numerical simulation and analytic work. First, we present the nonuniformity-smoothing effect of the radiation transport on implosion symmetry in an LIB ICF fuel pellet. The 2-D implosion simulation shows that the initial nonuniformity can be smoothed out well in an LIB ICF pellet; for example, the initial nonuniformity of 6% is smoothed to 0.07% during the implosion phase. In addition, linear analyses for the R-T instability under nonuniform acceleration in space and under radiation are also performed: The nonuniform acceleration field in space does not change the growth rate (γ) of the R-T instability. However, this nonuniformity may suppress the growth itself of the R-T instability. Radiation may reduc the growth rate (γ).

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42

Hora, Heinrich. "Turning point in pellet fusion by low density volume compression for a simplified fusion reactor." Fusion Engineering and Design 9 (January 1989): 407–12. http://dx.doi.org/10.1016/s0920-3796(89)80065-1.

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43

Hora, Heinrich. "Volume Ignition in Pellet Fusion to Overcome the Difficulties of Central Ignition." Zeitschrift für Naturforschung A 42, no. 10 (October 1, 1987): 1239–40. http://dx.doi.org/10.1515/zna-1987-1023.

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Since C. Yamanaka et al. demonstrated that the best fusion gains from laser irradiated pellets result only when central shocks are avoided and an ideal volume compression is achieved, the problems o f the central (spark) ignition with necessary densities of 1000 times the solid state may be overcome. Based on an analytical formula of volume ignition, the new conditions should provide reactor adequate laser fusion with compression to 50 to 100 times solid state.

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44

Inoue, Kazuko, and Tomio Ariyasu. "Sound waves and shock waves in high-density deuterium." Laser and Particle Beams 9, no. 4 (December 1991): 795–816. http://dx.doi.org/10.1017/s026303460000656x.

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The possibility of compressing the cryogenic hollow pellet of inertial confinement nuclear fusion with multiple adiabatic shock waves is discussed, on the basis of the estimation of the properties of a high-density deuterium plasma (1024−1027 cm−3, 10−1−104 eV), such as the velocity and the attenuation constant of the adiabatic sound wave, the width of the shock wave, and the surface tension.It is found that in the course of compression the wavelength of the adiabatic sound wave and the width of the weak shock wave sometimes become comparable to or exceed the fuel shell width of the pellet, and that the surface tension is negative. These results show that it is rather difficult to compress stably the hollow pellet with successive weak shock waves.

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45

KONISHI, Tadao, Hiroki YOSHIDA, and Yukio SAKAGAMI. "Accurate Mass Determination of an Electrodynamically Levitated Pellet for Laser Fusion." Review of Laser Engineering 26, no. 3 (1998): 265–67. http://dx.doi.org/10.2184/lsj.26.265.

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46

Gebhart, T. E., R. T. Holladay, M. J. Esmond, and A. L. Winfrey. "Optimization of Fusion Pellet Launch Velocity in an Electrothermal Mass Accelerator." Journal of Fusion Energy 33, no. 1 (October 1, 2013): 32–39. http://dx.doi.org/10.1007/s10894-013-9636-7.

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47

Gangradey, R., J. Mishra, S. Mukherjee, P. Panchal, P. Nayak, J. Agarwal, and Y. C. Saxena. "SPINS-IND: Pellet injector for fuelling of magnetically confined fusion systems." Review of Scientific Instruments 88, no. 6 (June 2017): 063503. http://dx.doi.org/10.1063/1.4985639.

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48

Azzerboni, B., E. Cardelli, M. Raugi, and A. Tellini. "Analysis of an arc-driven railgun for fusion fuel pellet injection." IEEE Transactions on Magnetics 26, no. 6 (1990): 3097–101. http://dx.doi.org/10.1109/20.102898.

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49

KAWATA, SHIGEO, TETSUO SOMEYA, TAKASHI NAKAMURA, SHUJI MIYAZAKI, KOJI SHIMIZU, and ALEKSANDAR I. OGOYSKI. "Heavy ion beam final transport through an insulator guide in heavy ion fusion." Laser and Particle Beams 21, no. 1 (January 2003): 27–32. http://dx.doi.org/10.1017/s0263034602211064.

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Key issues of heavy ion beam (HIB) inertial confinement fusion (ICF) include an efficient stable beam transport, beam focusing, uniform fuel pellet implosion, and so on. To realize a HIB fine focus on a fuel pellet, space-charge neutralization of incident focusing HIB is required at the HIB final transport just after a final focusing element in an HIB accelerator. In this article, an insulator annular tube guide is proposed at the final transport part, through which a HIB is transported. The physical mechanism of HIB charge neutralization based on an insulator annular guide is as follows: A local electric field created by HIB induces local discharges, and plasma is produced on the insulator inner surface. Then electrons are extracted from the plasma by the HIB net space charge. The electrons emitted neutralize the HIB space charge well.

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50

Huang, Yun Bao, Zi Rong Zeng, Shao En Jiang, Qi Fu Wang, and Li Ping Chen. "Compressive Sensing for the Symmetry Distribution Analysis of Thermal Radiation on the Capsule inside a Cylindrical Hohlraum." Advanced Materials Research 317-319 (August 2011): 511–15. http://dx.doi.org/10.4028/www.scientific.net/amr.317-319.511.

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The symmetric implosion of the pellet is very important in an inertial confinement fusion (ICF) system. The evaluation of symmetric distribution on the ICF pellet is time and memory consuming, especially when the elements of cylindrical hohlraums are iteratively subdivided. A novel compressive sensing (CS) based approach is presented in this paper to accurately valuate the distribution symmetry with much less computation. The core idea is that, the thermal radiation distribution is transformed in the spherical harmonic field, and the sparsity of spherical harmonics is accurately evaluated through CS approach. Finally, experiments are demonstrated to show higher efficiency of the proposed approach.

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