Maintainability of the helical reactor FFHR-c1 equipped with the liquid metal divertor and cartridge-type blankets

Miyazawa, J.; Goto, Takuya; Tamura, H.; Tanaka, Teruya; Yanagi, N.; Murase, T.; Sakamoto, R.; Masuzaki, S.; Ohgo, Takeru; Sagara, A.

doi:10.1016/j.fusengdes.2018.04.118

Cited by 11 publications

(12 citation statements)

References 17 publications

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“…In this way, conceptual design of the LHD-type helical fusion reactor FFHR-d1 has progressed, incorporating the time evolution of plasma profiles. A derivation of FFHR-d1, the so-called FFHR-c1, has also been designed with targeting year-long electric power generation by allowing for auxiliary heating along with innovative ideas for its engineering system [29].…”

Section: Conceptual Design Of the Lhd-type Helical Fusion Reactor Ffhmentioning

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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Section: Conceptual Design Of the Lhd-type Helical Fusion Reactor Ffhmentioning

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 device size is four times larger than the LHD [2], i.e., the major radius of the helical coils, R c , is 15.6 m in the FFHR-d1 and 3.9 m in the LHD. The magnetic field strength at the helical coil center, B c , is 4.7 T -5.6 T. The FFHR-c1 is the compact version of the FFHR-d1 with 0.7 times smaller device size (R c = 10.92 m) [3]. The FFHR-c1 is aiming at demonstration of one-year steadystate operation with self-produced fuel and electricity.…”

Section: Introductionmentioning

confidence: 99%

“…In the case of the helical reactor, how to construct the complicated structure within a realistic period of time is also an important issue. To realize easy construction and maintenance, a cartridge-type helical blanket system named the CARDISTRY-B (cartridges divided and inserted radially -blanket) has been proposed [3,6] based on the T-SHELL blanket concept [7]. The CARDISTRY-B is composed of the tritium breeding blanket (BB) filled with the flowing molten salt and the neutron shielding blanket (SB) filled with the tungsten carbide (WC).…”

Section: Introductionmentioning

confidence: 99%

Improved Design of a Cartridge-Type Helical Blanket System for the Helical Fusion Reactor FFHR-b1

Miyazawa

Tamura

Tanaka

et al. 2019

Plasma and Fusion Research

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The cartridge-type helical blanket system called the CARDISTRY-B has been proposed for the helical fusion reactor FFHR-d1. The CARDISTRY-B is aimed at easy construction and maintenance. However, there remain many issues in the design. For example, these include a large number of cartridges, no tangential ports, low compatibility with the helical divertor, and others. To solve these issues, an improved design of the cartridge-type blanket is proposed and named the CARDISTRY-B2. This is composed of the tritium breeding blanket (BB) filled with the flowing molten salt and the neutron shielding blanket (SB) filled with the tungsten-carbide. The number of the BB (or, SB) cartridges in the 1/10 section of the full torus are reduced from 32 to 17 (or, from 44 to 17). Tangential ports for the neutral beam injection heating are newly equipped together with the multipurpose blanket cartridge. Compatibility with the helical divertor is also improved. The BB cartridges are fixed on the fixing units set on the top of the SB. No other part of the BB is touching the SB except the fixing ribs. The SB cartridges surround the superconducting magnet coils and work as the cryostat inside the vacuum vessel. This makes the large bellows for the large maintenance ports unnecessary. Details of the CARDISTRY-B2 designed for a small helical fusion reactor FFHR-b1 are described in this paper.

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“…To solve this problem, "renewable" divertor concepts such as the liquid metal divertors and/or limiters [2][3][4][5], pebble divertors [6][7][8], etc., have been investigated. A liquid metal divertor named the REVOLVER-D (Reactor oriented Effectively VOLumetric VERtical Divertor) consisting of molten tin shower jets has been proposed for the helical fusion reactor FFHR [9,10]. Molten tin shower jets on the REVOLVER-D are inserted into the ergodic region of the plasma as a limiter/divertor.…”

Section: Introductionmentioning

confidence: 99%

A New Divertor System Using Fusible Metal Pebbles

Ohgo

Goto

Miyazawa

2019

Plasma and Fusion Research

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A fusible metal pebble divertor system named the REVOLVER-D2 is newly proposed here, based on the molten tin jet divertor REVOLVER-D and the pebble divertor concepts. In the REVOLVER-D2, solid tin pebble flows are used as the divertor target. Molten tin pools receive the falling tin pebbles to mitigate the impact of the heavy metal shower. All pebbles are melted in the molten tin pool and recycled into the tin pebbles again. The solid tin pebbles are formed inside the vacuum vessel by the shot tower method using silicone oil pools. This concept enables simultaneous achievement of a high heat load tolerance and a high evacuation efficiency, while mitigating the MHD effects. A high heat load can be removed by the pebble flow if the pebble size is large enough and the velocity is fast enough as with the molten tin jet. Although the charge up of pebbles affects the pebble motion due to the Lorentz force and the Coulomb force, the Lorentz force is negligible if the injection velocity is fast enough. For example, center-to-center pebble distance due to the Coulomb force will be ∼ 4 mm in the case of the injection velocity of 10 m/s if the molten tin pool is placed 2 m under the point where pebbles enter the ergodic layer.

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Maintainability of the helical reactor FFHR-c1 equipped with the liquid metal divertor and cartridge-type blankets

Cited by 11 publications

References 17 publications

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

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

Improved Design of a Cartridge-Type Helical Blanket System for the Helical Fusion Reactor FFHR-b1

A New Divertor System Using Fusible Metal Pebbles

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