Progress in inertial confinement fusion physics at Centre d'Etudes de Limeil-Valenton

André, M.; Babonneau, D.; Bayer, C.; Bernard, M.; Bocher, J. L.; Bruneau, J.; Coudeville, A.; Coutant, J.; Dautray, Robert; Decoster, A.; Decroisette, M.; Desenne, D.; Dufour, J.M.; Garconnet, J. P.; Holstein, P.A.; Jadaud, J. P.; Jolas, A.; Juraszek, D.; Lachkar, J.; Lascaux, P.; Breton, J-P. Le; Louis-Jacquet, M.; Meyer, Bernard De; Mucchielli, F.; Rousseaux, C.; Schirmann, D.; Schurtz, G.; Véron, D.; Watteau, J. P.

doi:10.1017/s0263034600008181

Cited by 4 publications

(3 citation statements)

References 20 publications

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“…The activation problem as well as the associated tritium problem is the focus of discussion for many years at very different reactor concepts~Velarde & Perlado, 2002;Tahir & Hoffmann, 1997;Perlado & Sanz, 1993;Beller et al, 1993!. Also, heavy ion drivers have to deal with activation problems due to beam losses~Mustafin et al, 2002;Fertman et al, 2002!. Certainly activation was extensively used as a good and efficient diagnosis of core performance in target implosioñ Azechi et al, 1991a, 1991b!, andappear in the routine activities of experimental inertial confinement facilities Manes et al, 1985;Andre et al, 1994!. In the field of computational modeling for safety and environmental~S&E! analysis, our main contribution refers to the computational system ACAB~Sanz, 2000!…”

Section: Activation Of Materials: Safety and Environmental Issuesmentioning

confidence: 99%

Activation and damage of fusion materials and tritium effects in inertial fusion reactors: Strategy for adequate irradiation

et al. 2005

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Long term research in low activation materials is being pursued in fusion programs and the assessment of allowable elements and0or impurities from safety and repository reasons are being studied at Instituto Fusión Nuclear~DENIM!, using ACAB code, for national ignition facility~NIF! and inertial fusion energy~IFE! reactors. Uncertainties in nuclear data are being considered, and experiments for validation of modeling will be presented. Multiscale simulation of radiation damage is now starting to be compared with experiments, and results on the simplest material can be reported as a function of impurities, temperature, and dose. Molecular dynamics~MD! allows us to identify stress-strain curve of FeCr ferritic steels under irradiation, and macroscopic conclusions can be advanced using simple models. However, a neutron source of enough intensity and adequate energy spectrum is needed which will be very peculiar in the case of pulsed IFE, as we claimed in past years. Development of international fusion materials irradiation facility~IFMIF! will be commented and compared with solutions such as spallation, and others using ultra-intense lasers for obtaining required irradiation magnitudes. Research on radiation damage in SiC composite is being pursued at macroscopic level, but basic knowledge is scarce. A systematic identification of type of stable defects is being presented with a new tight binding MD technique. Our research on simulation of silica irradiation damage will also be presented. The role of tritium, when elemental tritium~HT! and titrated water~HTO! derive in organically bound tritium~OBT! will be explained. The deposition and absorption processes are now being considered in our calculations giving more precision and accuracy to our conclusions of dosimetry effects. The role of HT versus HTO and the importance of re-emission process will be remarked, together with the long-term role of OBT.

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Section: Activation Of Materials: Safety and Environmental Issuesmentioning

confidence: 99%

Activation and damage of fusion materials and tritium effects in inertial fusion reactors: Strategy for adequate irradiation

et al. 2005

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“…However, indirect drive does increase energy losses through the wall and LEH's, it has a low coupling efficiency, and parametric instabilities may occur between an LEH and the wall. Indirect drive has been studied extensively using many different lasers [11][12][13] and underground nuclear explosives [14]. The primary focus of NIF is to demonstrate ignition and gain on the order of 10 using indirect drive.…”

Section: Hohlraum Modelingmentioning

confidence: 99%

“…7 at 8 ns. When the mesh is relaxed, the 13 material is left behind. The effectiveness of this approach depends on the resolution of the zoning.…”

Section: Late-time Hohlraum Expansionmentioning

confidence: 99%

Late-time simulation of National Ignition Facility hohlraums

et al. 2004

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The late-time (t ≥ 80 ns) behavior of hohlraums designed for the National Ignition Facility (NIF) is simulated using the multiphysics radiation hydrodynamics codes LASNEX and HYDRA. The spatial distribution of x-radiation outside the hohlraum is shown as a function of time. The energy spectrum of the x-ray emission is presented for various hohlraum viewing angles. We have made refinements to the grid motion algorithms in the arbitrary Lagrangian Eulerian (ALE) hydrodynamics code HYDRA to obtain the first late-time simulations of a hohlraum that can be used to give the spatial distribution of the vaporized hohlraum wall. The importance of late-time simulations in determining the lifetimes of debris shields on NIF is discussed.

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