2017
DOI: 10.1088/1741-4326/aa6a67
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Materials testing facilities and programmes for fission and ion implantation damage

Abstract: Currently there is no fusion neutron dedicated source with a high enough flux to mimic irradiation conditions relevant to those to be experienced by the First Wall in a fusion reactor. Nevertheless, very valuable information can be obtained from existing irradiation sources, in particular Materials Test Reactors, Fast neutron reactors and Ion accelerators. Partial information is provided by these irradiation facilities that can be used to down select main materials candidates for DEMO fusion reactors and evalu… Show more

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Cited by 21 publications
(18 citation statements)
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“…Options have been evaluated (such as a reduced specification version of IFMIF) to have the facility ready around the middle of the next decade and thus make available these data in time for the completion of the DEMO engineering design. This topic is discussed elsewhere in this special issue [32,33].…”
Section: Performance Requirements For Structural Materials For In-ves...mentioning
confidence: 99%
“…Options have been evaluated (such as a reduced specification version of IFMIF) to have the facility ready around the middle of the next decade and thus make available these data in time for the completion of the DEMO engineering design. This topic is discussed elsewhere in this special issue [32,33].…”
Section: Performance Requirements For Structural Materials For In-ves...mentioning
confidence: 99%
“…It is noted from Fig. (6) all the vacancies in structures simulated at 800 K and 1200K are located inside the vacancy clusters. Therefore, the X-Vac SRO parameters refer only to the chemical properties of solute elements nearby to voids or vacancy clusters.…”
Section: A Comparison Between Solute Re Os and Tamentioning
confidence: 83%
“…Design constraints based on the activation of reactor components limits material selection and necessitates the development of novel solutions for the high heat flux components. Tungsten is currently one of the leading candidate materials for these applications, however, there is a lack of data on its performance under realistic reactor conditions [5][6][7][8]. The combined effects of radiation damage and transmutation result in an increase in the inherent brittleness of W, a significant increase in its ductile to brittle transition temperature and radiation induced hardening [9].…”
Section: Introductionmentioning
confidence: 99%
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“…Critical to the resolution of both issues was the availability of an infrastructure of irradiation and post-irradiation facilities as well as experienced research teams able to focus and apply state-of-the-art techniques to develop the necessary insight [44].…”
Section: Materials Degradation During Servicementioning
confidence: 99%