Fuel Pellet Alignment in Heavy-Ion Inertial Fusion Reactor

Kubo, Takuya; Karino, T.; Kato, Hitoshi; Kawata, S.

doi:10.1109/tps.2018.2876471

Cited by 7 publications

(9 citation statements)

References 20 publications

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“…In ICF reactor, DT fuel target is repetitively injected and precisely aligned. When a spherical DT fuel is injected from outside a reactor, the DT fuel pellet is accelerated to a high speed of ~100 m/s to avoid the DT fuel melting by the reactor exhaust reactor gas [36][37][38][39][40][41]. Figure 4(b) shows a schematic diagram for the fuel target injection into a reactor chamber.…”

Section: Concept and Characteristics Of Heavy Ion Inertial Fusionmentioning

confidence: 99%

“…The stable fabrication of the fuel capsules is also important for the ICF reactor system [59][60][61][62][63]. When the cryo-target in Figure 3(a) is employed, the most outer layer of Pb becomes a superconductor [35][36][37] in a cryostat. The cryo-target is transferred to an injection gun, by which the cryo-target is injected into reactor.…”

Section: Concept and Characteristics Of Heavy Ion Inertial Fusionmentioning

confidence: 99%

“…The cryo-target is transferred to an injection gun, by which the cryo-target is injected into reactor. The traveling time of the fuel target injected is about 0.05 ~ 0.06 s [36], which is estimated by the traveling distance (~5-6 m) divided by the target injection speed of ~100 m/s. During the time interval of about 0.05 ~ 0.06 s, it was found that the superconducting state of the cryo-target is not melted [36].…”

Section: Concept and Characteristics Of Heavy Ion Inertial Fusionmentioning

confidence: 99%

“…In order to reach the high density, the fuel target implosion non-uniformity should be kept lower than a few percent [2,3,33,34]. The implosion non-uniformity of spherical fuel target comes from driver illumination non-uniformity, imperfect sphericity of fuel target, target injection alignment error into a fusion reactor, etc [35][36][37][38][39][40][41]. The high-density fuel compression is a major challenge in ICF.…”

Section: Introductionmentioning

confidence: 99%

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Direct-drive heavy ion beam inertial confinement fusion: a review, toward our future energy source

Kawata

2021

Advances in Physics: X

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Direct-drive heavy ion beam (HIB) inertial confinement fusion (ICF), or HIF would be a promising future energy source for society. Particle accelerators produce HIBs with precise particle energies, pulse lengths and pulse shapes with high energy efficiencies of ~30-40%. Higher energy driver efficiency means that a lower fusion energy output is required to construct a HIF power station to supply ~1 GW of electricity. A HIF power station could use about 4 to 5 MJ of HIB energy per shot at a shot rate of ~10 Hz. This review is focused on the direct-drive scheme in HIF. In directdrive fuel target HIBs deposit their energy into a shell surrounded by a denser tamping outer layer. The DT (Deuterium-Tritium) fusion fuel, with a total mass of several mg, must be compressed to about one thousand times solid density to reduce the input driver energy and to achieve an adequate burn fraction. Highdensity compression is a major challenge in ICF, requiring that non-uniformity in driver energy deposition be kept lower than a few percent. The axis of an HIB can be made to oscillate sufficiently rapidly to improve the uniformity of energy deposition.

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Section: Concept and Characteristics Of Heavy Ion Inertial Fusionmentioning

confidence: 99%

Section: Concept and Characteristics Of Heavy Ion Inertial Fusionmentioning

confidence: 99%

Section: Concept and Characteristics Of Heavy Ion Inertial Fusionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Direct-drive heavy ion beam inertial confinement fusion: a review, toward our future energy source

Kawata

2021

Advances in Physics: X

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“…The target production area includes high-precision technologies for target fabrication, injection and tracking. These technologies are currently an important research stage in the leading laboratories of the world [9][10][11][12][13][14][15][16][17][18]. Target compression and ignition is regarded as a major challenge to the IFE community.…”

Section: Introductionmentioning

confidence: 99%

In-Line Target Production for Laser IFE

Александрова¹,

Koshelev²,

Koresheva³

2020

Applied Sciences

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The paper presents the results of mathematical and experimental modeling of in-line production of inertial fusion energy (IFE) targets of a reactor-scaled design. The technical approach is the free-standing target (FST) layering method in line-moving spherical shells. This includes each step of the fabrication and injection processes in the FST transmission line (FST-TL) considered as a potential solution of the problem of mass target manufacturing. Finely, we discuss the development strategy of the FST-TL creation seeking to develop commercial power production based on laser IFE.

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Applications of Plasmas

Kawata

2023

Springer Series in Plasma Science and Technology

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Fuel Pellet Alignment in Heavy-Ion Inertial Fusion Reactor

Cited by 7 publications

References 20 publications

Direct-drive heavy ion beam inertial confinement fusion: a review, toward our future energy source

Direct-drive heavy ion beam inertial confinement fusion: a review, toward our future energy source

In-Line Target Production for Laser IFE

Applications of Plasmas

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