Progress in direct-drive inertial confinement fusion

R. L. McCrory; D. D. Meyerhofer; R. Betti; R. S. Craxton; J. A. Delettrez; D. H. Edgell; V. Yu Glebov; V. N. Goncharov; D. R. Harding; D. W. Jacobs-Perkins; J. P. Knauer; F. J. Marshall; P. W. McKenty; P. B. Radha; S. P. Regan; T. C. Sangster; W. Seka; R. W. Short; S. Skupsky; V. A. Smalyuk; J. M. Soures; C. Stoeckl; B. Yaakobi; D. Shvarts; J. A. Frenje; C. K. Li; R. D. Petrasso; F. H. Śguin

doi:10.1063/1.2837048

Progress in direct-drive inertial confinement fusion

R. L. McCrory, D. D. Meyerhofer, R. Betti, R. S. Craxton, J. A. Delettrez, D. H. Edgell, V. Yu Glebov, V. N. Goncharov, D. R. Harding, D. W. Jacobs-Perkins, J. P. Knauer, F. J. Marshall, P. W. McKenty, P. B. Radha, S. P. Regan, T. C. Sangster, W. Seka, R. W. Short, S. Skupsky, V. A. SmalyukJ. M. Soures, C. Stoeckl, B. Yaakobi, D. Shvarts, J. A. Frenje, C. K. Li, R. D. Petrasso, F. H. Śguin

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Abstract

Significant progress in direct-drive inertial confinement fusion (ICF) research has been made since the completion of the 60-beam, 30- kJUV OMEGA Laser System [Boehly, Opt. Commun. 133, 495 (1997)] in 1995. A theory of ignition requirements, applicable to any ICF concept, has been developed. Detailed understanding of laser-plasma coupling, electron thermal transport, and hot-electron preheating has lead to the measurement of neutron-averaged areal densities of ∼200 mg cm2 in cryogenic target implosions. These correspond to an estimated peak fuel density in excess of 100 g cm3 and are in good agreement with hydrodynamic simulations. The implosions were performed using an 18-kJ drive pulse designed to put the converging fuel on an adiabat of two. The polar-drive concept will allow direct-drive-ignition research on the National Ignition Facility while it is configured for indirect drive. Advanced ICF ignition concepts-fast ignition [Tabak, Phys. Plasmas 1, 1626 (1994)] and shock ignition [Betti, Phys. Rev. Lett. 98, 155001 (2007)] -have the potential to significantly reduce ignition driver energies and/or provide higher target gain.

Original language	English
Article number	055503
Journal	Physics of Plasmas
Volume	15
Issue number	5
DOIs	https://doi.org/10.1063/1.2837048
State	Published - 9 Jun 2008
Externally published	Yes

ASJC Scopus subject areas

Condensed Matter Physics

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

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McCrory, R. L., Meyerhofer, D. D., Betti, R., Craxton, R. S., Delettrez, J. A., Edgell, D. H., Glebov, V. Y., Goncharov, V. N., Harding, D. R., Jacobs-Perkins, D. W., Knauer, J. P., Marshall, F. J., McKenty, P. W., Radha, P. B., Regan, S. P., Sangster, T. C., Seka, W., Short, R. W., Skupsky, S., ... Śguin, F. H. (2008). Progress in direct-drive inertial confinement fusion. Physics of Plasmas, 15(5), Article 055503. https://doi.org/10.1063/1.2837048

@article{397fa59d4d654b9894d9966a9435d50a,

title = "Progress in direct-drive inertial confinement fusion",

abstract = "Significant progress in direct-drive inertial confinement fusion (ICF) research has been made since the completion of the 60-beam, 30- kJUV OMEGA Laser System [Boehly, Opt. Commun. 133, 495 (1997)] in 1995. A theory of ignition requirements, applicable to any ICF concept, has been developed. Detailed understanding of laser-plasma coupling, electron thermal transport, and hot-electron preheating has lead to the measurement of neutron-averaged areal densities of ∼200 mg cm2 in cryogenic target implosions. These correspond to an estimated peak fuel density in excess of 100 g cm3 and are in good agreement with hydrodynamic simulations. The implosions were performed using an 18-kJ drive pulse designed to put the converging fuel on an adiabat of two. The polar-drive concept will allow direct-drive-ignition research on the National Ignition Facility while it is configured for indirect drive. Advanced ICF ignition concepts-fast ignition [Tabak, Phys. Plasmas 1, 1626 (1994)] and shock ignition [Betti, Phys. Rev. Lett. 98, 155001 (2007)] -have the potential to significantly reduce ignition driver energies and/or provide higher target gain.",

author = "McCrory, {R. L.} and Meyerhofer, {D. D.} and R. Betti and Craxton, {R. S.} and Delettrez, {J. A.} and Edgell, {D. H.} and Glebov, {V. Yu} and Goncharov, {V. N.} and Harding, {D. R.} and Jacobs-Perkins, {D. W.} and Knauer, {J. P.} and Marshall, {F. J.} and McKenty, {P. W.} and Radha, {P. B.} and Regan, {S. P.} and Sangster, {T. C.} and W. Seka and Short, {R. W.} and S. Skupsky and Smalyuk, {V. A.} and Soures, {J. M.} and C. Stoeckl and B. Yaakobi and D. Shvarts and Frenje, {J. A.} and Li, {C. K.} and Petrasso, {R. D.} and {\'S}guin, {F. H.}",

note = "Funding Information: This work was supported by the U.S. Department of Energy Office of Inertial Confinement Fusion under Cooperative Agreement No. DE-FC52-92SF19460, the University of Rochester, and the New York State Energy Research and Development Authority. The support of the DOE does not constitute an endorsement by the DOE of the views expressed in this article.",

year = "2008",

month = jun,

day = "9",

doi = "10.1063/1.2837048",

language = "English",

volume = "15",

journal = "Physics of Plasmas",

issn = "1070-664X",

publisher = "American Institute of Physics",

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McCrory, RL, Meyerhofer, DD, Betti, R, Craxton, RS, Delettrez, JA, Edgell, DH, Glebov, VY, Goncharov, VN, Harding, DR, Jacobs-Perkins, DW, Knauer, JP, Marshall, FJ, McKenty, PW, Radha, PB, Regan, SP, Sangster, TC, Seka, W, Short, RW, Skupsky, S, Smalyuk, VA, Soures, JM, Stoeckl, C, Yaakobi, B, Shvarts, D, Frenje, JA, Li, CK, Petrasso, RD & Śguin, FH 2008, 'Progress in direct-drive inertial confinement fusion', Physics of Plasmas, vol. 15, no. 5, 055503. https://doi.org/10.1063/1.2837048

TY - JOUR

T1 - Progress in direct-drive inertial confinement fusion

AU - McCrory, R. L.

AU - Meyerhofer, D. D.

AU - Betti, R.

AU - Craxton, R. S.

AU - Delettrez, J. A.

AU - Edgell, D. H.

AU - Glebov, V. Yu

AU - Goncharov, V. N.

AU - Harding, D. R.

AU - Jacobs-Perkins, D. W.

AU - Knauer, J. P.

AU - Marshall, F. J.

AU - McKenty, P. W.

AU - Radha, P. B.

AU - Regan, S. P.

AU - Sangster, T. C.

AU - Seka, W.

AU - Short, R. W.

AU - Skupsky, S.

AU - Smalyuk, V. A.

AU - Soures, J. M.

AU - Stoeckl, C.

AU - Yaakobi, B.

AU - Shvarts, D.

AU - Frenje, J. A.

AU - Li, C. K.

AU - Petrasso, R. D.

AU - Śguin, F. H.

N1 - Funding Information: This work was supported by the U.S. Department of Energy Office of Inertial Confinement Fusion under Cooperative Agreement No. DE-FC52-92SF19460, the University of Rochester, and the New York State Energy Research and Development Authority. The support of the DOE does not constitute an endorsement by the DOE of the views expressed in this article.

PY - 2008/6/9

Y1 - 2008/6/9

N2 - Significant progress in direct-drive inertial confinement fusion (ICF) research has been made since the completion of the 60-beam, 30- kJUV OMEGA Laser System [Boehly, Opt. Commun. 133, 495 (1997)] in 1995. A theory of ignition requirements, applicable to any ICF concept, has been developed. Detailed understanding of laser-plasma coupling, electron thermal transport, and hot-electron preheating has lead to the measurement of neutron-averaged areal densities of ∼200 mg cm2 in cryogenic target implosions. These correspond to an estimated peak fuel density in excess of 100 g cm3 and are in good agreement with hydrodynamic simulations. The implosions were performed using an 18-kJ drive pulse designed to put the converging fuel on an adiabat of two. The polar-drive concept will allow direct-drive-ignition research on the National Ignition Facility while it is configured for indirect drive. Advanced ICF ignition concepts-fast ignition [Tabak, Phys. Plasmas 1, 1626 (1994)] and shock ignition [Betti, Phys. Rev. Lett. 98, 155001 (2007)] -have the potential to significantly reduce ignition driver energies and/or provide higher target gain.

AB - Significant progress in direct-drive inertial confinement fusion (ICF) research has been made since the completion of the 60-beam, 30- kJUV OMEGA Laser System [Boehly, Opt. Commun. 133, 495 (1997)] in 1995. A theory of ignition requirements, applicable to any ICF concept, has been developed. Detailed understanding of laser-plasma coupling, electron thermal transport, and hot-electron preheating has lead to the measurement of neutron-averaged areal densities of ∼200 mg cm2 in cryogenic target implosions. These correspond to an estimated peak fuel density in excess of 100 g cm3 and are in good agreement with hydrodynamic simulations. The implosions were performed using an 18-kJ drive pulse designed to put the converging fuel on an adiabat of two. The polar-drive concept will allow direct-drive-ignition research on the National Ignition Facility while it is configured for indirect drive. Advanced ICF ignition concepts-fast ignition [Tabak, Phys. Plasmas 1, 1626 (1994)] and shock ignition [Betti, Phys. Rev. Lett. 98, 155001 (2007)] -have the potential to significantly reduce ignition driver energies and/or provide higher target gain.

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U2 - 10.1063/1.2837048

DO - 10.1063/1.2837048

M3 - Article

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SN - 1070-664X

VL - 15

JO - Physics of Plasmas

JF - Physics of Plasmas

IS - 5

M1 - 055503

ER -

Progress in direct-drive inertial confinement fusion

Abstract

ASJC Scopus subject areas

UN SDGs

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