Electrical insulating property of ceramic coating materials in radiation and high-temperature environment

Tanaka, Teruya; Nagayasu, R.; Sawada, Akihiko; Ikeda, T.; Sato, F.; Suzuki, Akihiro; Muroga, T.; Iida, Toshiyuki

doi:10.1016/j.jnucmat.2007.03.207

Cited by 21 publications

(5 citation statements)

References 12 publications

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“…This is about two orders of magnitude less than the estimated upper limit (100 S m −2 ) [146]. In the case of Er 2 O 3 , although there are differences for the different samples tested, the available RIC data for bulk and thin coatings are in reasonable agreement, as may be seen in figure 14 for gamma irradiation, and figure 15 for electron irradiation [159,160]. The RIC for gamma irradiation (≈10 −11 S m −1 at 4.5 Gy s −1 , 0.3 MV m −1 , figure 14) and that for electron irradiation at a low dose (≈4 × 10 −9 S m −1 at 700 Gy s −1 , 1.3 MV m −1 , figure 15) indicate an almost linear dose rate dependence.…”

Section: Coating Materials For Blanketsmentioning

confidence: 66%

“…Available radiation testing data for suitably coated structural materials are very limited. Candidate ceramic materials in both coating on steels and bulk form have been examined for electrical conductivity (RIC) under gamma, electron, and neutron irradiation [158][159][160]. For all the materials tested, the extrapolated RIC at ≈1 kGy s −1 (FW region) is ⩽10 −6 S m −1 , leading to a conductivity of about 1 S m −2 for a 1 µm thick coating.…”

Section: Coating Materials For Blanketsmentioning

confidence: 99%

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Functional materials for tokamak in-vessel systems—status and developments

2017

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The challenge to be faced in ITER and DEMO, as well as future fusion power plants (PPs), by the insulating (functional) materials for use not only in the magnetic coils and heating systems but for safety and control diagnostics is daunting. The available data on thermomechanical properties (strength, swelling, thermal conductivity) indicate that suitable materials are available for doses >1 dpa. However, for the important physical properties which degrade at far lower doses, data are generally only available for doses 1 dpa, corresponding at most to ITER expectations. To address this, the selection and development of potential radiation hard materials and components for diagnostic, H&CD, and other systems for DEMO and PPs is urgently needed, and will also assist in defining the materials test requirements for materials test reactors and IFMIF. This paper reviews the current data and basic knowledge for materials required for optical, DC electric, and AC/RF dielectric applications. A short discussion of the associated R&D needs/requirements deduced from missing or limited irradiation data is also presented.

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Section: Coating Materials For Blanketsmentioning

confidence: 66%

Section: Coating Materials For Blanketsmentioning

confidence: 99%

Functional materials for tokamak in-vessel systems—status and developments

2017

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“…The RIC was evaluated as a function of the dose rate for Er 2 O 3 , Y 2 O 3 and CaZrO 3 using 14 MeV neutrons, fission neutrons and ␥-rays, in comparison with data on Al 2 O 3 [43,44]. It was confirmed that the RIC of the candidate materials was almost proportional to the dose rate and weakly dependent on radiation species from low dose rate of ∼10 −3 Gy/s to high dose rate of ∼10 2 Gy/s.…”

Section: Radiation Effects and Radiation Induced Conductivity (Ric)mentioning

confidence: 99%

Progress in the development of insulator coating for liquid lithium blankets

Muroga

Pint

2010

Fusion Engineering and Design

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“…Irradiation is one of the most important factors affecting their electrical insulating performance. It was recently found that degradation of insulating performance, due to radiation-induced electrical conductivity (RIC), depends weakly on temperature and will not prevent the achievement of the required performance in the high temperature and radiation environment of the breeding blanket [144]. Multilayer coatings also appear promising: a metallic vanadium or vanadium alloy layer would prevent lithium from interacting with the underlying ceramic insulating layer (e.g.…”

Section: Main Issues For Further Development Of Vanadium-based Materi...mentioning

confidence: 99%

Status of R&D activities on materials for fusion power reactors

Baluc

Abe

Boutard³

et al. 2007

Nucl. Fusion

142

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Current R&D activities on materials for fusion power reactors are mainly focused on plasma facing, structural and tritium breeding materials for plasma facing (first wall, divertor) and breeding blanket components. Most of these activities are being performed in Europe, Japan, the People's Republic of China, Russia and the USA. They relate to the development of new high temperature, radiation resistant materials, the development of coatings that will act as erosion, corrosion, permeation and/or electrical/MHD barriers, characterization of candidate materials in terms of mechanical and physical properties, assessment of irradiation effects, compatibility experiments, development of reliable joints, and development and/or validation of design rules. Priorities defined worldwide in the field of materials for fusion power reactors are summarized, as well as the main achievements obtained during the last few years and the near-term perspectives in the different investigation areas.

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Electrical insulating property of ceramic coating materials in radiation and high-temperature environment

Cited by 21 publications

References 12 publications

Functional materials for tokamak in-vessel systems—status and developments

Functional materials for tokamak in-vessel systems—status and developments

Progress in the development of insulator coating for liquid lithium blankets

Status of R&D activities on materials for fusion power reactors

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