Radiation Effects on the Physical Properties of Dielectric Insulators for Fusion Reactors

Hodgson, E.R.; Shikama, Tatsuo

doi:10.1016/b978-0-08-056033-5.00126-9

Cited by 7 publications

(21 citation statements)

References 171 publications

(169 reference statements)

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“…Hence, for the numerous dielectric mat erials, we expect ionizing and displacement dose rates ranging from less than 1 Gy s −1 to ≈1000 Gy s −1 , <10 −11 to ≈10 −8 dpa s −1 . This will lead to ionizing doses up to >200 GGy, and displacement doses of many dpa, see table 1 [3,5,6]. Although these are estimated extrapolations, they agree very well with recent calculations for the expected total dose at the inner wall of the DEMO vacuum vessel [12].…”

Section: Radiation Levelssupporting

confidence: 84%

“…Several earlier reviews have given overviews of the results of irradiation testing on suitable functional materials for ITER heating and diagnostic systems, as well as in-depth discussion of relevant radiation effects and problems associated with adequate testing [1][2][3][4][5]. The longer-term problems beyond ITER, where one must address the development of materials and components capable of surviving for extended periods in the more hostile environment of not only DEMO but fusion PPs have also been recently reviewed [6], as well as the need for tritium generation, which will require dedicated systems and materials [4].…”

Section: Introductionmentioning

confidence: 99%

“…Due to the urgent necessity to address potential problems within the limit for ITER materials performance requirements [5,6], currently in general only design-oriented data at low doses are available. Even at these low doses problems have been identified.…”

Section: Introductionmentioning

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: Radiation Levelssupporting

confidence: 84%

Section: Introductionmentioning

confidence: 99%

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

2017

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“…(j) As for all fusion energy systems, insulating materials feature significantly in many components including high-voltage neutral-beam insulators, dielectrics in radio-frequency systems and standoffs for biased limiters, direct energy conversion grids and also feedback actuators. Robust ceramics are needed (Hodgson & Shikama 2012).…”

Section: Technology Gapsmentioning

confidence: 99%

Prospects for a high-field, compact break-even axisymmetric mirror (BEAM) and applications

Forest,

Anderson,

Endrizzi

et al. 2024

J. Plasma Phys.

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This paper explores the feasibility of a break-even-class mirror referred to as BEAM (break-even axisymmetric mirror): a neutral-beam-heated simple mirror capable of thermonuclear-grade parameters and $Q\sim 1$ conditions. Compared with earlier mirror experiments in the 1980s, BEAM would have: higher-energy neutral beams, a larger and denser plasma at higher magnetic field, both an edge and a core and capabilities to address both magnetohydrodynamic and kinetic stability of the simple mirror in higher-temperature plasmas. Axisymmetry and high-field magnets make this possible at a modest scale enabling a short development time and lower capital cost. Such a $Q\sim 1$ configuration will be useful as a fusion technology development platform, in which tritium handling, materials and blankets can be tested in a real fusion environment, and as a base for development of higher- $Q$ mirrors.

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“…Wirth et al 213 and Duffy 214 highlighted the numerous multiscale modeling grand challenges in particular the plasma materials interactions, the extreme heat and particle flux environments and complexity of extracting the tritium from breeder blankets, and the large and time-varying thermomechanical stresses in structural materials all subject to 14.1 MeV neutrons causing extensive irradiation damage, which has significant effects on thermal, mechanical and electrical properties. 215 Snead and Ferraris 216 highlight the current use and future potential for carbon as a plasma facing material in tokamaks. Potential fusion applications of UHTCs include in tokamak diverters and plasma facing materials.…”

Section: July 2013 Advanced Ceramics and Compositesmentioning

confidence: 99%

Opportunities for Advanced Ceramics and Composites in the Nuclear Sector

et al. 2013

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Ceramics have played a crucial role in the development of fission based nuclear power, in glass & glass composite high level wasteforms, in composite cements to encapsulate intermediate level wastes (ILW) and also for oxide nuclear fuels based on UO2 and PuO2/UO2 mixed oxides. They are also used as porous filters with the ability to absorb radionuclides (RN) from air and liquids and are playing a key role in the cleanup at Fukushima. Non‐oxides also find current fission applications including in graphite moderators and B4C control rods. Ceramics will continue to be significant in the near‐term expansion of nuclear power via next‐step developments of fuels with inert matrices or based on thoria and in wasteforms using alternative composite cements or single or multiphase ceramics that can host Pu & other difficult RN. Longer term advances for Generation IV reactors, which will operate at higher temperatures & with higher fuel burn‐up require innovative fuel developments potentially via carbides & nitrides or composite fuel systems. Novel non‐thermal (cement‐like) and thermal techniques are currently being developed to treat some of the difficult legacy wastes. Non‐thermally derived wasteforms developed from geopolymers, composite cements, hydroceramics, and phosphate‐bonded ceramics and thermally derived wasteforms made by Hot Isostatic Pressing and fluidized bed steam reforming (FBSR) as well as vitrification techniques based on cold crucible melting (CCM), Joule‐heater in‐container melting and plasma melting (PM) are described. Future developments in waste treatment will be based on separation technologies for partitioning individual RN along with design & construction of RN‐containing ceramic targets for inducing transmutation reactions. Near demonstration actinide‐hosting ceramic wasteforms including multiphase Synroc systems are described. Opportunities also exist for ceramics in structural applications in Generation IV reactors such as composite SiC/SiC and C/C for fuel cladding and control rods and MAX phases and ultrahigh‐temperature ceramics (UHTCs) may find near core fuel coating and cladding applications. Uses of ceramics in fusion reactor systems will be both functional (ceramic superconductors in magnet systems for plasma control and in Li silicate breeder blankets in tokamaks) and structural including as sapphire diagnostic windows, graphite diverters, and plasma facing C and UHTCs. In all these cases, performance is limited by poorly understood radiation damage and interface controlled processes, which demands a combined modeling/experimental approach.

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Radiation Effects on the Physical Properties of Dielectric Insulators for Fusion Reactors

Cited by 7 publications

References 171 publications

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

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

Prospects for a high-field, compact break-even axisymmetric mirror (BEAM) and applications

Opportunities for Advanced Ceramics and Composites in the Nuclear Sector

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