Investigation of liquid-film formation along first wall of laser-fusion reactor

Kawara, Zensaku; Yamamoto, Kunihiro; Kunugi, Tomoaki; Norimatsu, T.

doi:10.1016/j.fusengdes.2010.08.026

Cited by 6 publications

(4 citation statements)

References 1 publication

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“…Issues related to the wet wall will be tested during this phase. These issues include chamber evacuation to achieve 4 Hz operation, liquid first wall stability [26], final optics contamination, beam port protection [27], surface material erosion via liquid LiPb, LiPb impurity control, and tritium flow in the system [28,29].…”

Section: Chamber System and Radiation Safetymentioning

confidence: 99%

Conceptual design and issues of the laser inertial fusion test (LIFT) reactor—targets and chamber systems

et al. 2017

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We present the conceptual design of an experimental laser fusion plant known as the laser inertial fusion test (LIFT) reactor. The conceptual design aims at technically connecting a single-shot experiment and a commercial power plant. The LIFT reactor is designed on a three-phase scheme, where each phase has specific goals and the dedicated chambers of each phase are driven by the same laser. Technical issues related to the chamber technology including radiation safety to repeat burst mode operation are discussed in this paper.

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Section: Chamber System and Radiation Safetymentioning

confidence: 99%

Conceptual design and issues of the laser inertial fusion test (LIFT) reactor—targets and chamber systems

et al. 2017

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“…Liquid metals interest fusion science researchers engaged in developing innovative fusion-related devices, such as the first walls of inertial confinement fusion reactors [1,2] and magnetic confinement fusion reactors [3,4], diverters [5], blankets [6], and liquid Li target flow at the International Fusion Materials Irradiation Facility (IFMIF) [7]. The removal of the ultra-high heat loads from plasmas and beams is a crucial engineering issue in such devices.…”

Section: Liquid-metal Free-surface Flow Applications In Fusion Enginementioning

confidence: 99%

Free-Surface Characteristics of a Liquid Li Wall Jet

Kanemura

Kondo

Sugiura

et al. 2016

Plasma and Fusion Research

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In this study, the free-surface characteristics of a liquid Li wall jet for the Li target of the International Fusion Materials Irradiation Facility (IFMIF) are comprehensively reviewed. In developing the IFMIF Li target, a scientific understanding of the free-surface wave characteristics and the development of diagnostic tools to measure these characteristics were critical issues. The same issues must be faced in other liquid metal applications in fusion engineering, such as liquid first walls or liquid diverters. Thus far, diagnostic tools and methods to measure all of the characteristics of waves (i.e., wavelength, wave period, wave speed (free-surface speed), wave height (amplitude)), and average jet thickness have been developed, and the probability distributions applicable to these wave parameters, as well as their statistical characteristic values, have been determined, validating the stability of the IFMIF Li target. Our findings, both the wave characteristics and the diagnostic tools, can be applied to not only the IFMIF Li target but also innovative liquid metal diverters or first walls in fusion engineering. Issues pertaining to liquid-metal freesurface flow applicationsIn general, liquid metals are used at high temperatures. Corrosion and erosion damage of structural materials must be reduced to ensure long-term system integrity. In particular, when using liquid Li, a popular metal in fusion en-

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“…The initial temperature of liquid lead and the coolant temperature are 823.15 K according to the operating conditions of KOYO-fast [1][2][3]. The initial thickness of liquid lead is 0.3 cm because it was found that liquid-film flow could be stably established with thickness of 0.3 -0.5 cm [9][10][11].…”

Section: Two-dimensional Simulation Models [4-6]mentioning

confidence: 99%

Two-Dimensional Simulation of a Plume Produced by Ablation in the Liquid Wall Chamber of KOYO-Fast

Furukawa

Norimatsu

2016

Plasma and Fusion Research

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An integrated two-dimensional ablation simulation code DECORE-2D (DEsign COde for REactor) has been developed to estimate the environment of the liquid wall chamber of KOYO-fast. Density profiles of ablated lead are estimated using DECORE-2D for the case of first ignition with 200 MJ fusion power output. To discuss the stagnation of ablated materials in the chamber, the divergence of ablated material with phase change was analyzed in two-dimensional planar geometry. The spread angle of a plume obtained by this simulation is roughly 1 •. This result indicates that the stagnation of ablated materials can be discussed with straight flows from tiles tilted by 30 • to the tangential direction.

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Investigation of liquid-film formation along first wall of laser-fusion reactor

Cited by 6 publications

References 1 publication

Conceptual design and issues of the laser inertial fusion test (LIFT) reactor—targets and chamber systems

Conceptual design and issues of the laser inertial fusion test (LIFT) reactor—targets and chamber systems

Free-Surface Characteristics of a Liquid Li Wall Jet

Two-Dimensional Simulation of a Plume Produced by Ablation in the Liquid Wall Chamber of KOYO-Fast

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