The experimental plan for cryogenic layered target implosions on the National Ignition Facility - The inertial confinement approach to fusion
Creators
- Edwards, M. J.1
- Lindl, J. D.1
- Spears, B. K.1
- Weber, S. V.1
- Atherton, L. J.1
- Bleuel, D. L.1
- Bradley, D. K.1
- Callahan, D. A.1
- Cerjan, C. J.1
- Clark, D1
- Collins, G. W.1
- Fair, J. E.1
- Fortner, R. J.1
- Glenzer, S. H.1
- Haan, S. W.1
- Hammel, B. A.1
- Hamza, A. V.1
- Hatchett, S. P.1
- Izumi, N.1
- Jacoby, B.1
- and others
- 1. Lawrence Livermore National Laboratory, Livermore, California 94550 (United States)
Description
Ignition requires precisely controlled, high convergence implosions to assemble a dense shell of deuterium-tritium (DT) fuel with ρR>∼1 g/cm2 surrounding a 10 keV hot spot with ρR ∼ 0.3 g/cm2. A working definition of ignition has been a yield of ∼1 MJ. At this yield the α-particle energy deposited in the fuel would have been ∼200 kJ, which is already ∼10 x more than the kinetic energy of a typical implosion. The National Ignition Campaign includes low yield implosions with dudded fuel layers to study and optimize the hydrodynamic assembly of the fuel in a diagnostics rich environment. The fuel is a mixture of tritium-hydrogen-deuterium (THD) with a density equivalent to DT. The fraction of D can be adjusted to control the neutron yield. Yields of ∼1014-15 14 MeV (primary) neutrons are adequate to diagnose the hot spot as well as the dense fuel properties via down scattering of the primary neutrons. X-ray imaging diagnostics can function in this low yield environment providing additional information about the assembled fuel either by imaging the photons emitted by the hot central plasma, or by active probing of the dense shell by a separate high energy short pulse flash. The planned use of these targets and diagnostics to assess and optimize the assembly of the fuel and how this relates to the predicted performance of DT targets is described. It is found that a good predictor of DT target performance is the THD measurable parameter, Experimental Ignition Threshold Factor, ITFX ∼ Y x dsf 2.3, where Y is the measured neutron yield between 13 and 15 MeV, and dsf is the down scattered neutron fraction defined as the ratio of neutrons between 10 and 12 MeV and those between 13 and 15 MeV.
Additional details
Identifiers
- DOI
- 10.1063/1.3592173;
Publishing Information
- Journal Title
- Physics of Plasmas
- Journal Volume
- 18
- Journal Issue
- 5
- Journal Page Range
- p. 051003-051003.23
- ISSN
- 1070-664X
- CODEN
- PHPAEN
INIS
- Country of Publication
- United States
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 43016792
- Subject category
- S07: ISOTOPES AND RADIATION SOURCES;
- Descriptors DEI
- DEUTERIUM; HYDROGEN; IGNITION; INERTIAL CONFINEMENT; PLASMA DENSITY; PLASMA DIAGNOSTICS; THERMONUCLEAR FUELS; TRITIUM; US NATIONAL IGNITION FACILITY
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CONFINEMENT; ELEMENTS; FUELS; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; NONMETALS; NUCLEI; ODD-EVEN NUCLEI; ODD-ODD NUCLEI; PLASMA CONFINEMENT; RADIOISOTOPES; STABLE ISOTOPES; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- (c) 2011 American Institute of Physics