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Dive into the research topics where R. J. Leeper is active.

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Featured researches published by R. J. Leeper.


Physics of Plasmas | 2014

Investigation of ion kinetic effects in direct-drive exploding-pusher implosions at the NIF

Michael Rosenberg; Alex Zylstra; F. H. Séguin; H. G. Rinderknecht; Johan A. Frenje; M. Gatu Johnson; H. Sio; C. Waugh; N. Sinenian; C. K. Li; R. D. Petrasso; P.W. McKenty; M. Hohenberger; P. B. Radha; J. A. Delettrez; V. Yu. Glebov; R. Betti; V.N. Goncharov; J. P. Knauer; T. C. Sangster; S. LePape; A. J. Mackinnon; J. Pino; J. M. McNaney; J. R. Rygg; Peter A. Amendt; C. Bellei; L. R. Benedetti; L. Berzak Hopkins; R. Bionta

Measurements of yield, ion temperature, areal density (ρR), shell convergence, and bang time have been obtained in shock-driven, D2 and D3He gas-filled “exploding-pusher” inertial confinement fusion (ICF) implosions at the National Ignition Facility to assess the impact of ion kinetic effects. These measurements probed the shock convergence phase of ICF implosions, a critical stage in hot-spot ignition experiments. The data complement previous studies of kinetic effects in shock-driven implosions. Ion temperature and fuel ρR inferred from fusion-product spectroscopy are used to estimate the ion-ion mean free path in the gas. A trend of decreasing yields relative to the predictions of 2D draco hydrodynamics simulations with increasing Knudsen number (the ratio of ion-ion mean free path to minimum shell radius) suggests that ion kinetic effects are increasingly impacting the hot fuel region, in general agreement with previous results. The long mean free path conditions giving rise to ion kinetic effects in ...


Physical Review Letters | 2016

First Liquid Layer Inertial Confinement Fusion Implosions at the National Ignition Facility.

R.E. Olson; R. J. Leeper; J. L. Kline; A. Zylstra; S. A. Yi; Juergen Biener; T. Braun; B. J. Kozioziemski; J. Sater; P. A. Bradley; Robert R. Peterson; Brian M. Haines; L. Yin; L. Berzak Hopkins; N. B. Meezan; C. Walters; M. M. Biener; C. Kong; J. Crippen; G. A. Kyrala; R. C. Shah; H. W. Herrmann; D. C. Wilson; Alex V. Hamza; A. Nikroo; S. H. Batha

The first cryogenic deuterium and deuterium-tritium liquid layer implosions at the National Ignition Facility (NIF) demonstrate D_{2} and DT layer inertial confinement fusion (ICF) implosions that can access a low-to-moderate hot-spot convergence ratio (1230) DT ice layer implosions. Although high CR is desirable in an idealized 1D sense, it amplifies the deleterious effects of asymmetries. To date, these asymmetries prevented the achievement of ignition at the NIF and are the major cause of simulation-experiment disagreement. In the initial liquid layer experiments, high neutron yields were achieved with CRs of 12-17, and the hot-spot formation is well understood, demonstrated by a good agreement between the experimental data and the radiation hydrodynamic simulations. These initial experiments open a new NIF experimental capability that provides an opportunity to explore the relationship between hot-spot convergence ratio and the robustness of hot-spot formation during ICF implosions.


Fusion Science and Technology | 2016

The National Ignition Facility Diagnostic Set at the Completion of the National Ignition Campaign, September 2012

J. D. Kilkenny; P. M. Bell; David K. Bradley; D. L. Bleuel; J. A. Caggiano; E. L. Dewald; W. W. Hsing; D. H. Kalantar; R. L. Kauffman; D. J. Larson; D. L. Moody; D. Schneider; M. B. Schneider; D. Shaughnessy; R. T. Shelton; W. Stoeffl; K. Widmann; C. B. Yeamans; S. H. Batha; Gary P. Grim; H. W. Herrmann; F. E. Merrill; R. J. Leeper; John A. Oertel; T. C. Sangster; D. H. Edgell; M. Hohenberger; V. Yu. Glebov; S. P. Regan; J. A. Frenje

Abstract At the completion of the National Ignition Campaign (NIC), the National Ignition Facility (NIF) had about 36 different types of diagnostics. These were based on several decades of development on Nova and OMEGA and involved the whole U.S. inertial confinement fusion community. In 1994, the Joint Central Diagnostic Team documented a plan for a limited set of NIF diagnostics in the NIF Conceptual Design Report. Two decades later, these diagnostics, and many others, were installed workhorse tools for all users of NIF. We give a short description of each of the 36 different types of NIC diagnostics grouped by the function of the diagnostics, namely, target drive, target response and target assembly, stagnation, and burn. A comparison of NIF diagnostics with the Nova diagnostics shows that the NIF diagnostic capability is broadly equivalent to that of Nova in 1999. Although NIF diagnostics have a much greater degree of automation and rigor than Nova’s, new diagnostics are limited such as the higher-speed X-ray imager. Recommendations for future diagnostics on the NIF are discussed.


Physics of Plasmas | 2017

The effects of convergence ratio on the implosion behavior of DT layered inertial confinement fusion capsules

Brian M. Haines; S. A. Yi; R. E. Olson; S. F. Khan; G. A. Kyrala; A. Zylstra; P. A. Bradley; Robert R. Peterson; J. L. Kline; R. J. Leeper; R. C. Shah

The wetted foam capsule design for inertial confinement fusion capsules, which includes a foam layer wetted with deuterium-tritium liquid, enables layered capsule implosions with a wide range of hot-spot convergence ratios (CR) on the National Ignition Facility. We present a full-scale wetted foam capsule design that demonstrates high gain in one-dimensional simulations. In these simulations, increasing the convergence ratio leads to an improved capsule yield due to higher hot-spot temperatures and increased fuel areal density. High-resolution two-dimensional simulations of this design are presented with detailed and well resolved models for the capsule fill tube, support tent, surface roughness, and predicted asymmetries in the x-ray drive. Our modeling of these asymmetries is validated by comparisons with available experimental data. In 2D simulations of the full-scale wetted foam capsule design, jetting caused by the fill tube is prevented by the expansion of the tungsten-doped shell layer due to prehe...


Journal of Physics: Conference Series | 2016

Wetted foam liquid fuel ICF target experiments

R. E. Olson; R. J. Leeper; S. A. Yi; J. L. Kline; A. Zylstra; Robert R. Peterson; R. C. Shah; T. Braun; Juergen Biener; B. J. Kozioziemski; J. Sater; M. M. Biener; Alex V. Hamza; A. Nikroo; L. Berzak Hopkins; D. Ho; S. LePape; N. B. Meezan

We are developing a new NIF experimental platform that employs wetted foam liquid fuel layer ICF capsules. We will use the liquid fuel layer capsules in a NIF sub-scale experimental campaign to explore the relationship between hot spot convergence ratio (CR) and the predictability of hot spot formation. DT liquid layer ICF capsules allow for flexibility in hot spot CR via the adjustment of the initial cryogenic capsule temperature and, hence, DT vapor density. Our hypothesis is that the predictive capability of hot spot formation is robust and 1D-like for a relatively low CR hot spot (CR~15), but will become less reliable as hot spot CR is increased to CR>20. Simulations indicate that backing off on hot spot CR is an excellent way to reduce capsule instability growth and to improve robustness to low-mode x-ray flux asymmetries. In the initial experiments, we will test our hypothesis by measuring hot spot size, neutron yield, ion temperature, and burn width to infer hot spot pressure and compare to predictions for implosions with hot spot CRs in the range of 12 to 25. Larger scale experiments are also being designed, and we will advance from sub-scale to full-scale NIF experiments to determine if 1D-like behavior at low CR is retained as the scale-size is increased. The long-term objective is to develop a liquid fuel layer ICF capsule platform with robust thermonuclear burn, modest CR, and significant α-heating with burn propagation.


Physics of Plasmas | 2018

Variable convergence liquid layer implosions on the National Ignition Facility

A. Zylstra; S. A. Yi; Brian M. Haines; R. E. Olson; R. J. Leeper; T. Braun; Juergen Biener; J. L. Kline; S. H. Batha; L. Berzak Hopkins; S. Bhandarkar; P. A. Bradley; J. Crippen; M. Farrell; D. N. Fittinghoff; H. W. Herrmann; H. Huang; S. F. Khan; C. Kong; B. J. Kozioziemski; G. A. Kyrala; T. Ma; N. B. Meezan; F. E. Merrill; A. Nikroo; Robert R. Peterson; N. Rice; J. Sater; R. C. Shah; Michael Stadermann

Liquid layer implosions using the “wetted foam” technique, where the liquid fuel is wicked into a supporting foam, have been recently conducted on the National Ignition Facility for the first time [Olson et al., Phys. Rev. Lett. 117, 245001 (2016)]. We report on a series of wetted foam implosions where the convergence ratio was varied between 12 and 20. Reduced nuclear performance is observed as convergence ratio increases. 2-D radiation-hydrodynamics simulations accurately capture the performance at convergence ratios (CR)u2009∼u200912, but we observe a significant discrepancy at CRu2009∼u200920. This may be due to suppressed hot-spot formation or an anomalous energy loss mechanism.


High Energy Density Physics | 2016

A direct-drive exploding-pusher implosion as the first step in development of a monoenergetic charged-particle backlighting platform at the National Ignition Facility

M. Rosenberg; Alex Zylstra; F. H. Séguin; H. G. Rinderknecht; J. A. Frenje; M. Gatu Johnson; H. Sio; C. Waugh; N. Sinenian; C. K. Li; R. D. Petrasso; S. LePape; T. Ma; A. J. Mackinnon; J. R. Rygg; Peter A. Amendt; C. Bellei; L.R. Benedetti; L. Berzak Hopkins; R. Bionta; D. T. Casey; L. Divol; M. J. Edwards; S. Glenn; S. H. Glenzer; D. G. Hicks; J. R. Kimbrough; O. L. Landen; J. D. Lindl; A. G. MacPhee


Bulletin of the American Physical Society | 2016

Modeling of low convergence liquid layer wetted foam implosions at the National Ignition Facility

S. A. Yi; R.E. Olson; L. Yin; D. C. Wilson; H. W. Herrmann; A. Zylstra; Brian M. Haines; Robert R. Peterson; P. A. Bradley; R. C. Shah; J. L. Kline; R. J. Leeper; S. H. Batha; J. L. Milovich; L. Berzak Hopkins; D. Ho; N. B. Meezan


Bulletin of the American Physical Society | 2015

Wetted Foam Liquid Fuel ICF Target Experiments

R. E. Olson; R. J. Leeper; A. Yi; A. Zylstra; J. L. Kline; Robert R. Peterson; T. Braun; Juergen Biener; M. M. Biener; B. J. Kozioziemski; J. Sater; Alex V. Hamza; A. Nikroo; L. Berzak Hopkins; S. LePape; A. J. Mackinnon; N. B. Meezan


Bulletin of the American Physical Society | 2015

Design Options for the High-Foot Ignition Capsule Series on NIF

T. R. Dittrich; O. A. Hurricane; L. Berzak Hopkins; D. A. Callahan; D. S. Clark; T. Doeppner; S. W. Haan; B. A. Hammel; J.A. Harte; D. E. Hinkel; T. Ma; A. Pak; H.-S. Park; J. D. Salmonson; C. R. Weber; G. Zimmerman; R.E. Olson; J. L. Kline; R. J. Leeper

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L. Berzak Hopkins

Lawrence Livermore National Laboratory

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J. L. Kline

Los Alamos National Laboratory

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Robert R. Peterson

Los Alamos National Laboratory

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A. Zylstra

Los Alamos National Laboratory

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N. B. Meezan

Lawrence Livermore National Laboratory

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R. C. Shah

Los Alamos National Laboratory

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R. E. Olson

Los Alamos National Laboratory

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S. A. Yi

Los Alamos National Laboratory

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S. LePape

Lawrence Livermore National Laboratory

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A. J. Mackinnon

Lawrence Livermore National Laboratory

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