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A new Multiple Beams–Material Interaction Research Facility for radiation damage studies in fusion materials

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TLDR
In order to obtain clear understandings of radiation damage in fusion materials, as well as the dynamic material behavior under severe environments in advanced energy systems, such as fusion reactors, fission reactors, a Multiple Beams-Material Interaction Research Facility (DuET facility) has been constructed at the Institute of Advanced Energy, Kyoto University, in these three years.
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This article is published in Fusion Engineering and Design.The article was published on 2000-11-01. It has received 91 citations till now. The article focuses on the topics: Fusion power.

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A new approach to evaluate irradiation hardening of ion-irradiated ferritic alloys by nano-indentation techniques

TL;DR: In this article, the authors investigated the irradiation hardening of Fe-based model ferritic alloys after Fe-ion irradiation experiments in order to deduce mechanistically based nominal hardness from the nano-indentation tests on the ion-irradiated surface.
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Microstructural development in cubic silicon carbide during irradiation at elevated temperatures

TL;DR: In this article, the development of chemically vapor-deposited (CVD) high-purity beta-SiC during neutron and self-ion irradiation at elevated temperatures was studied.
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Evaluation of Helium effects on swelling behavior of oxide dispersion strengthened ferritic steels under ion irradiation

TL;DR: In this paper, the effects of ion-irradiation on the swelling behavior were investigated for a high-chromium oxide dispersion strengthened (ODS) ferritic steel and a 9Cr-2W reduced-activation ferritic (RAF) steel up to a high dose (nominal 60 dpa) with and without helium (900 appm) by using single and dual-ion irradiation techniques at 773 K.
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Silicon carbide and its composites for nuclear applications – Historical overview

TL;DR: Sil carbide materials have seen extensive study for over half a century in support of nuclear power systems as mentioned in this paper, which has led to the development of irradiation-hardened materials that are currently in use for fission reactor fuels and available as structural composites for next generation reactors.
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The influences of irradiation temperature and helium production on the dimensional stability of silicon carbide

TL;DR: In this paper, the influence of irradiation temperature and helium production on fluence-dependent swelling behavior in cubic SiC were characterized following the establishment of an experimental technique to determine ion-irradiation-induced swelling within an accuracy of 200 °C.
References
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Book

Handbook of modern ion beam materials analysis

TL;DR: The Handbook of Modern Ion Beam Materials Analysis, Second Edition is a compilation of updated techniques and data for use in the ion-beam analysis of materials, written and compiled by over 30 leading authorities in the field of ion beam analysis.

Effects of radiation on materials

TL;DR: In this paper, tensile properties of neutron irradiated A212B pressure vessel steel, fracture resistance of irradiated stainless steel clad vessels, and radiation damage calculations for compound materials are discussed.
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Mechanisms of helium interaction with radiation effects in metals and alloys: A review

TL;DR: In this article, an extended treatment of the critical cavity radius concept is developed, covering the temperature extension of swelling by gas, the evolution of bimodal cavity size distributions and the necessity for gas as a prerequisite to swelling under some conditions.
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Recent advances in the development of SiC/SiC as a fusion structural material

TL;DR: In this article, SiC fibers and fiber/matrix interfaces made with porous SiC and multi-layer SiC/C/SiC are developed to minimize the presence of C in the interface for improved radiation and chemical stability of the composite materials.
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Progress in vanadium alloy development for fusion applications

TL;DR: In this paper, the authors presented an update on the experimental results on candidate low activation vanadium alloys, including the V-4Cr-4Ti and V-Cr-Ti Alloy.
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