Extended capability of the integrated transport analysis suite, TASK3D-a, for LHD experiment

Yokoyama, M.; Seki, R.; Suzuki, C.; Sato, Motoyasu; Emoto, M.; Murakami, S.; Osakabe, M.; Tsujimura, Toru Ii; Yoshimura, Y.; Ido, T.; Ogawa, K.; Satake, S.; Suzuki, Y.; Goto, Takuya; Ida, K.; Pablant, N.; Gates, D.; Warmer, F.; Vincenzi, P.

doi:10.1088/1741-4326/aa800a

Cited by 32 publications

(37 citation statements)

References 33 publications

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“…It is important for evaluation of neutron emission rate with considering the practical plasma profile and the ratio of deuteron in plasma. To introduce the FIT3D-DD code to the transport analysis suite, TASK3D-a [7], we designed a new neutron emission rate evaluation tool with author's e-mail: seki.ryohsuke@lhd.nifs.ac.jp * ) This article is based on the presentation at the 27th International Toki Conference (ITC27) & the 13th Asia Pacific Plasma Theory Conference (APPTC2018).…”

Section: Introductionmentioning

confidence: 99%

Evaluation of Neutron Emission Rate with FIT3D-DD Code in Large Helical Device

Seki

Ogawa

Isobe

et al. 2019

Plasma and Fusion Research

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We compared the experimentally measured neutron emission rate with the emission rate calculated by using the simple Fokker-Planck equation with the experimental temperature and density profiles, and the deuteron density evaluated by a spectroscopy in peripheral region in LHD. The neutron emission rates evaluated by the FIT3D-DD code are approximately two times higher than experimental results in the typical magnetic configuration of LHD. In the case of low fast-ion confinement, the calculations are approximately four times higher than experimental measurements.

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Section: Introductionmentioning

confidence: 99%

Evaluation of Neutron Emission Rate with FIT3D-DD Code in Large Helical Device

Seki

Ogawa

Isobe

et al. 2019

Plasma and Fusion Research

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“…The global parameters are significantly affected by the change in the plasma volume caused by the RMP application. In order to study the local plasma transport characteristics, a core plasma energy transport has been analyzed with the 1-D transport code TASK3D [33]. This code calculates the heating source profile, in the present case by the NBI, by taking into account the beam slowing down and solves a heat conduction equation with n e and T e values measured experimentally.…”

Section: Compatibility With Core Plasma Performancementioning

confidence: 99%

Experimental Studies of and Theoretical Models for Detachment in Helical Fusion Devices

Kobayashi¹,

Tokar²

2020

Fusion Energy

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Good plasma performance in magnetic fusion devices of different types, both tokamaks and helical devices, is achieved normally if the plasma density does not exceed a certain limit. In devices with a divertor, such as tokamaks JET, JT-60U, and heliotron large helical device (LHD), by approaching the density limit, the plasma detaches from the divertor target plates so that the particle and heat fluxes onto the targets reduce dramatically. This is an attractive scenario for fusion reactors, offering a solution to the plasma-wall interaction problem. However, the main concerns by realizing such a scenario are the stability of the detached zone. The activity on the heliotron LHD aimed on detachment stabilization, by applying a resonant magnetic perturbation (RMP) and generating a wide magnetic island at the plasma edge, will be reviewed. Also, theoretical models, explaining the detachment conditions, low-frequency oscillations at the detachment onset, and mechanisms of the detached plasma stabilization by RMP, will be discussed.

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“…Scenario developments have been conducted based on the time evolution of plasma radial profiles by solving 1D transport equations. Since this 1D transport code merely employs a simple empirical transport model deduced from LHD experimental results, consistency with detailed physics criteria such as MHD stability and neoclassical transport should be checked by integrating numerical modules for physics analyses [28] that are being or were already validated by LHD experiments. Using these models, control algorithms of auxiliary heating power and fueling amounts have been examined to reach the identified operation point.…”

Section: Lhd As a Platform For Wide-ranging Plasma Researchmentioning

confidence: 99%

Advanced Helical Plasma Research towards a Steady-State Fusion Reactor by Deuterium Experiments in Large Helical Device

Takeiri

2018

Atoms

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The Large Helical Device (LHD) is one of the world’s largest superconducting helical system fusion-experiment devices. Since the start of experiments in 1998, it has expanded its parameter regime. It has also demonstrated world-leading steady-state operation. Based on this progress, the LHD has moved on to the advanced research phase, that is, deuterium experiment, which started in March 2017. During the first deuterium experiment campaign, an ion temperature of 10 keV was achieved. This was a milestone in helical systems research: demonstrating one of the conditions for fusion. All of this progress and increased understanding have provided the basis for designing an LHD-type steady-state helical fusion reactor. Moreover, LHD plasmas have been utilized not only for fusion research, but also for diagnostics development and applications in wide-ranging plasma research. A few examples of such contributions of LHD plasmas (spectroscopic study and the development of a new type of interferometer) are introduced in this paper.

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Extended capability of the integrated transport analysis suite, TASK3D-a, for LHD experiment

Cited by 32 publications

References 33 publications

Evaluation of Neutron Emission Rate with FIT3D-DD Code in Large Helical Device

Evaluation of Neutron Emission Rate with FIT3D-DD Code in Large Helical Device

Experimental Studies of and Theoretical Models for Detachment in Helical Fusion Devices

Advanced Helical Plasma Research towards a Steady-State Fusion Reactor by Deuterium Experiments in Large Helical Device

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