Materials testing facilities and programmes for fission and ion implantation damage

Vicente, S.M. González de; Boutard, Jean-Louis; Zinkle, S.J.; Tanigawa, Hiroyasu

doi:10.1088/1741-4326/aa6a67

Cited by 21 publications

(18 citation statements)

References 68 publications

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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%

European DEMO design strategy and consequences for materials

Federici¹,

et al. 2017

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Demonstrating the production of net electricity and operating with a closed fuel-cycle remain unarguably the crucial steps towards the exploitation of fusion power. These are the aims of a demonstration fusion reactor (DEMO) proposed to be built after ITER. This paper briefly describes the DEMO design options that are being considered in Europe for the current conceptual design studies as part of the Roadmap to Fusion Electricity Horizon 2020. These are not intended to represent fixed and exclusive design choices but rather 'proxies' of possible plant design options to be used to identify generic design/material issues that need to be resolved in future fusion reactor systems. The materials nuclear design requirements and the effects of radiation damage are briefly analysed with emphasis on a pulsed 'low extrapolation' system, which is being used for the initial design integration studies, based as far as possible on mature technologies and reliable regimes of operation (to be extrapolated from the ITER experience), and on the use of materials suitable for the expected level of neutron fluence. The main technical issues arising from the plasma and nuclear loads and the effects of radiation damage particularly on the structural and heat sink materials of the vessel and in-vessel components are critically discussed. The need to establish realistic target performance and a development schedule for near-term electricity production tends to favour more conservative technology choices. The readiness of the technical (physics and technology) assumptions that are being made is expected to be an important factor for the selection of the technical features of the device.

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Section: Performance Requirements For Structural Materials For In-ves...mentioning

confidence: 99%

European DEMO design strategy and consequences for materials

Federici¹,

et al. 2017

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“…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%

“…In the absence of a dedicated high-intensity 14.1 MeV neutron source, multi-scale materials modelling based on first-principles calculations is an indispensable tool for exploring the irradiation conditions similar to those to be experienced by the first wall in a fusion reactor [6,8,[44][45][46][47][48][49][50][51][52][53][54][55][56][57][58]. Precipitation of non-equilibrium phases in irradiated material is a commonly observed phenomenon and is a result of radiation induced segregation (RIS), whereas radiation enhanced diffusion (RED) can lead to a faster rate of formation of equilibrium phases [59][60][61][62][63][64][65].…”

Section: Introductionmentioning

confidence: 99%

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First principles model for voids decorated by transmutation solutes: Short-range order effects and application to neutron irradiated tungsten

Nguyen-Manh,

Wrobel,

Klimenkov

et al. 2021

Preprint

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Understanding how properties of materials change due to nuclear transmutations is a major challenge for the design of structural components for a fusion power plant. In this study, by combining a first-principles matrix Hamiltonian approach with thermodynamic integration we investigate quasisteady state configurations of multi-component alloys, containing defects, over a broad range of temperature and composition. The model enables simulating transmutation-induced segregation effects in materials, including tungsten where the phenomenon is strongly pronounced. Finite-temperature analysis shows that voids are decorated by Re and Os, but there is no decoration by tantalum (Ta). The difference between the elements is correlated with the sign of the short range order (SRO) parameter between impurity and vacancy species, in agreement with Atom Probe Tomography (APT) observations of irradiated W-Re, W-Os, W-Ta alloys in the solid solution limit. Statistical analyses of Re and Os impurities in vacancy-rich tungsten show that the SRO effects involving the two solutes are highly sensitive to the background concentration the species. In quaternary W-Re-Os-Vac alloys containing 1.5% Re and 0.1% Os, the SRO Re-Os parameter is negative at 1200K, driving the formation of concentrated Re and Os precipitates. Comparison with experimental Transmission Electron Microscopy (TEM) and APT data on W samples irradiated at the High Flux Reactor (HFR) shows that the model explains the origin of anomalous segregation of transmutation products (Re,Os) to vacancy clusters and voids in the high temperature limit pertinent to the operating conditions of a fusion power plant.

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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%

Lessons learnt from fission materials R&D programmes

English

Buckthorpe

2017

Nucl. Fusion

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The purpose of this paper is to review the lessons learnt on the use of advanced materials on the design and operation of components in fission reactors and to consider how these lessons can be employed to benefit the use of advanced structural and, to a certain extent, coolant channel materials in the design and qualification of the in-vessel and containment vessel components for the DEMO fusion reactor. The focus is on lessons learnt on methodologies that need to be applied, and a number of specific recommendations are made.

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Materials testing facilities and programmes for fission and ion implantation damage

Cited by 21 publications

References 68 publications

European DEMO design strategy and consequences for materials

European DEMO design strategy and consequences for materials

First principles model for voids decorated by transmutation solutes: Short-range order effects and application to neutron irradiated tungsten

Lessons learnt from fission materials R&D programmes

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