What is. Inertial Confinement Fusion?

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Transcription:

What is Inertial Confinement Fusion?

Inertial Confinement Fusion: dense & short-lived plasma Fusing D and T requires temperature to overcome Coulomb repulsion density & confinement time to maximize number of reactions MCF: low density plasma confined by B fields over minutes or more ICF: high density plasma confined very briefly by its own inertia ICF is a pulsed process Areal density (rr) is a key parameter for efficient burn (fuel burns before it deconfines) for reasonable driver & yield energies Hot spot ignition needed to make up for low laser and hydrodynamic efficiencies: fusion reactions start in heated fuel and spread to neighboring cold fuel

Laser-driven ICF uses intense laser beams to compress and heat a small pellet of DT fuel IGNITION COMPRESSION HEATING & ABLATION BURN PROPAGATION The obvious way: direct drive The mainstream way: indirect drive

Physics issues associated with indirect-drive ICF Capsule shape and stability Control low-mode symmetry & high-mode hydrodynamic instabilities Capsule compression Implode fuel with proper timing and strength of shocks Ignition and Burn Trigger and propagate burn wave Laser-Plasma Interaction Propagate intense beams in long, low-density plasma X-ray conversion Absorb laser energy and re-emitt as x-rays Design relies heavily on complex, multiphysics, radiative hydrodynamics codes

ICF research status the National Ignition Facility (USA)

NIF-0000-00000s2.ppt Author NIC Review, December 2009 7

NIF has made good progress towards demonstrating target and laser performance required for ignition The latest shot had a total yield of 6.2x10 15 at a Tion = 4.9 kev November 2013 The a (or self heating) yield equaled the compression yield This a-doubling is an important step towards achieving fusion ignition December 2011

The National Ignition Campaign on NIF had to face two major difficulties: velocity and mix Radiation drive produced in the hohlraum is in reasonnable agreement with predictions, but implosion velocity of capsule systematically below prediction Pressure in hot spot and yield remain low, suggesting more mix of ablator in fuel than expected, quenching fusion - Changing the pulse shape has improved mix control, and enabled record neutron yields, but scheme does not extrapolate to ignition target - Clear experimental progress, but offset with simulation still holds

M. J. Edwards (LLNL), IFSA 2013:

ICF research status the Laser Mégajoule (France)

Laser Mégajoule main characteristics 4 Laser bays Glass Neodymium laser, frequency tripled : l = 0.35 µm Pulse duration : from 0.3 ns to 25 ns Designed for 240 beams, 176 will be installed Laser energy > 1.3 MJ, Power > 400 TW 60m H 38m Target area Biological protection : 2 m thick concrete Target chamber Ø 10 m Ignition target 2 X 2 cones irradiation : 33 & 49 Hohlraum length ~ cm Capsule Ø ~ 2 mm DT cryogenic layer

The four laser bays are (nearly) complete Bay South-East 7 bundles+ PETAL completed end 2011 Bay South-West 6 bundles will be completed end 2013 Bay North-East 5 bundles completed end 2011 Bay North-West 5 bundles completed end 2012

LMJ is a key component of the CEA «Simulation Program» to guarantee a safe and reliable French Deterrent w/o testing Design and Guarantee of nuclear warheads now relies on numerical simulation codes Progress in physical models and numerical tools is obtained through prediction and comparison with dedicated experimental results This experimental program is executed on LIL a prototype LMJ quad delivering 15 kj (CEA, Cesta, France), shut down 2014 Omega a 60 beam, 30 kj facility at LLE (U. Rochester, USA), uses NIC results as much as possible will benefit from initial LMJ experiments starting at the end of 2014 Gain demonstration on LMJ is a long term objective simulation codes must first be improved to be consistent with NIF results

l o g T [ K ] 20% of LMJ time will be open to academic access The «Institut Laser et Plasmas» brings together the French academic community on laser plasmas, and will organize access to LMJ for civilian research Direct-drive ICF Laboratory Astrophysics Materials and High Energy Density Physics Acceleration and High Energy Physics 10 G RB γ S upe rnova proge ni t ors 8 I C F FINAL LMJ / PETAL 6 P (t ot a l )=1M ba r 4 2 Ioni z e d U ni oni z e d Now (LULI 2000, Omega, Gekko ) INITIAL LMJ / PETAL -5 0 +5 +10 l og ρ [g/ c m 3 ]

ICF research effort worldwide GSI PALS RAL AWE LULI LLE CEA/CESTA VNIIEF CAEP KAERI LLNL SNL LANL NRL SIOM ILE Location of the major High Energy Density laser facilities worldwide