2020
DOI: 10.1088/1741-4326/ab5d5f
|View full text |Cite
|
Sign up to set email alerts
|

Predicting spherical symmetry degeneration of non-infrared deuterium ice layer in a cryogenic capsule

Abstract: A cylindrical cryogenic target containing deuterium fuel acts as an important surrogate to help understand implosion physics before the deuterium-tritium capability is brought online. Uniformity of the deuterium ice thickness is a key parameter for the inertial confinement fusion (ICF) experiments. Achieving and retaining a uniform deuterium ice layer in capsule without infrared radiation is difficult in engineering. The method used to calculate the ice thickness deviation of deuterium-tritium fuel is invalid … Show more

Help me understand this report

Search citation statements

Order By: Relevance

Paper Sections

Select...
1
1

Citation Types

0
2
0

Year Published

2020
2020
2024
2024

Publication Types

Select...
7

Relationship

0
7

Authors

Journals

citations
Cited by 8 publications
(2 citation statements)
references
References 54 publications
0
2
0
Order By: Relevance
“…The perturbation transfer from the ablator to the substrate is demonstrated to happen from the very first moments of the interaction within the TEP phase. Further investigations are in progress to study the transfer efficiency of these perturbations from the ablator to the substrate for direct-drive target designs [48,49]. In particular, plastic (polystyrene CH) [50] and Beryllium [51] ablators on ice DD substrates are being examined in spherical geometry including the use of thin Au overcoatings with different thicknesses.…”
Section: Resultsmentioning
confidence: 99%
“…The perturbation transfer from the ablator to the substrate is demonstrated to happen from the very first moments of the interaction within the TEP phase. Further investigations are in progress to study the transfer efficiency of these perturbations from the ablator to the substrate for direct-drive target designs [48,49]. In particular, plastic (polystyrene CH) [50] and Beryllium [51] ablators on ice DD substrates are being examined in spherical geometry including the use of thin Au overcoatings with different thicknesses.…”
Section: Resultsmentioning
confidence: 99%
“…In general, the non-hydrogen gas content inside the capsule should be lower than 205 ppm, and the non-helium gas content inside the hohlraum should be lower than 8250 ppm [9]. Currently, the impurity gases are mainly removed from the capsule and hohlraum by sub-atmospheric purging, i.e., evacuation and filling cycles, through microcapillaries that are only tens of microns in diameter [10][11][12][13]. Since the capsule and hohlraum volumes are too small to take measurements in situ, accurately predicting the flow characteristics inside the microtubes and the chambers is critical for the purging of the target.…”
Section: Introductionmentioning
confidence: 99%