Progress and challenges of the ITER TBM Program from the IO perspective

Giancarli, L.; Barabash, V.; Campbell, D.J.; Chiocchio, S.; Cordier, J.J.; Dammann, A.; Dell’Orco, G.; Elbez-Uzan, Joëlle; Fourneron, Jean-Marc; Friconneau, Jean-Pierre; Gasparotto, M.; Iseli, Markus; Jung, Chulwoo; Kim, Byoung Yoon; Lazarov, D.; Levesy, B.; Loughlin, M.; Merola, M.; Nevière, J.-C.; Romain, P.; Ring, William; Schneiderova, Iva; Willms, Scott; Siarras, A.; Shu, W.M.; Snipes, J.; Laan, J.G. van der

doi:10.1016/j.fusengdes.2015.11.046

Cited by 26 publications

(11 citation statements)

References 11 publications

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“…The investigated beryllium pebbles with a diameter of about 1 mm were fabricated by NGK Insulators Ltd., Japan using the rotating electrode method 49 . Their chemical composition is given in Table 2 50 and the parameters of irradiation, performed in the High Flux Reactor (HFR) Petten within the HIDOBE 2 campaign 4 , are shown in Table 1. The irradiation temperatures within the rigs, which were continuously controlled during irradiation with thermocouples, showed large variations.…”

Section: Discussionmentioning

confidence: 99%

“…In nuclear fusion technology, beryllium is considered as a "First Wall" material in ITER, presently one of the largest mankind projects worldwide [3][4][5] , but also as a neutron multiplier material in different tritium-breeding blanket concepts for the future demonstration fusion power plant DEMO 6,7 . In one of the blanket concepts, called helium-cooled pebble bed (HCPB), interchanged layers of a lithium ceramic and beryllium pebbles will be used.…”

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confidence: 99%

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New insights into microstructure of irradiated beryllium based on experiments and computer simulations

Klimenkov

Vladimirov

Jäntsch

et al. 2020

Sci Rep

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The microstructural response of beryllium after neutron irradiation at various temperatures (643-923 K) was systematically studied using analytical transmission electron microscope that together with outcomes from advanced atomistic modelling provides new insights in the mechanisms of microstructural changes in this material. The most prominent feature of microstructural modification is the formation of gas bubbles, which is revealed at all studied irradiation temperatures. except for the lowest irradiation temperature, gas bubbles have the shape of thin hexagonal prisms with average height and diameter increasing with temperature. A high number density of small bubbles is observed within grains, while significantly larger bubbles are formed along high-angle grain boundaries (GB). Denuded zones (DZ) nearly free from bubbles are found along both high-and low-angle grain boundaries. Precipitations of secondary phases (mainly intermetallic Al-Fe-Be) were observed inside grains, along dislocation lines and at GBs. EDX analysis has revealed homogeneous segregation of chromium and iron along GBs. the observed features are discussed with respect to the available atomistic modelling results. in particular, we present a plausible reasoning for the abundant formation of gas bubbles on intermetallic precipitates, observation of various thickness of zones denuded in gas bubbles and precipitates, and their relation to the atomic scale diffusion mechanisms of solute-vacancy clusters.

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Section: Discussionmentioning

confidence: 99%

mentioning

confidence: 99%

New insights into microstructure of irradiated beryllium based on experiments and computer simulations

Klimenkov

Vladimirov

Jäntsch

et al. 2020

Sci Rep

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“…Based on each IM's R&D results, six TBM concepts have been selected for the testing in the ITER. The selected TBMs with their characteristics and ITER equatorial port allocation are shown in Table .…”

Section: Main Features Of the Tbms And Their Integration In Itermentioning

confidence: 99%

“…The main functions of the TBB are to generate tritium, extract heat from the neutron, and contribute to shielding. ITER provides a unique opportunity to test the test blanket module (TBM) in DEMO relevant conditions, and the TBM testing is important in accomplishing the ITER missions on the assessment of technological feasibility of fusion energy . The TBM testing answers whether the tritium can be sufficiently generated in the blanket to compensate for the tritium consumed in the fusion reaction, and whether the high temperature heat can be extracted from the blanket for efficient electricity generation.…”

Section: Introductionmentioning

confidence: 99%

Overview of ITER TBM program objectives and management

Hong

2017

Int J Energy Res

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SUMMARYOne of the most important ITER missions is to test tritium breeding blanket (TBB) concepts that would result in tritium self-sufficiency, an extraction of high grade heat and net electricity production in future fusion reactors. Knowledge of the TBB performance characteristics in the integrated fusion nuclear environment is essential to designing the TBB of the DEMO and the fusion reactor. Three equatorial ports in ITER are allotted for testing test blanket modules (TBMs), which are mock-ups of the TBB, allowing up to six TBMs to be simultaneously installed and tested -two TBMs per each port. Conceptual designs for all TBM systems are now completed, and the important next milestones are the achievement of the preliminary and the final design by 2025. The TBM systems will be installed during Assembly Phase III, which is planned to start in 2030, and tested during the ITER Pre-Fusion Power Operation 2, which is planned to start in 2032. This paper describes the objectives and management aspects of the TBM Program.

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“…Controlled fusion energy is the most significant solution for contributing to energy betterment without polluting the environment. , Tritium breeder materials have played a pivotal role in the test blanket module of the deuterium–tritium fusion reactor due to the tritium production from breeder materials at the time of the reaction process. − Lithium-based ceramics are one of best prospects for tritium breeding materials because of their high lithium density, competent tritium release performance, commendable thermal conductivity, favorable chemical stability, prominent antiradiation capability, and compatibility with other blanket modules. − Among these properties, lithium density has a direct bearing on the tritium breeding ratio; in these materials, the value of lithium density is as large as possible . Over the last several decades, immense amounts of research have been conducted on tritium breeding materials both here and abroad.…”

Section: Introductionmentioning

confidence: 99%

Characterization of a Li₄TiO₄ Tritium Breeder by First-Principles Calculation and an Experimental Approach

Yan

Chen

et al. 2021

ACS Appl. Energy Mater.

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A tetralithium titanium (Li 4 TiO 4 ) compound is a tritium breeder material that deserves serious consideration for the fusion reactor blanket concept because of its high lithium density. In the current research, an experimental investigation was conducted for the first time to verify the calculated simulation results. First, the lattice parameters, energy band structures, and thermodynamic properties of Li 4 TiO 4 are investigated by means of first-principles density functional theory. Then, the Li 4 TiO 4 powder was synthesized via a solid-state reaction. Subsequently, the samples were systematically characterized using various measurement techniques. The products of the ultraviolet diffuse reflection spectrum, Raman spectroscopy, and laser thermal conductivity are consistent with the theoretical calculations.

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Progress and challenges of the ITER TBM Program from the IO perspective

Cited by 26 publications

References 11 publications

New insights into microstructure of irradiated beryllium based on experiments and computer simulations

New insights into microstructure of irradiated beryllium based on experiments and computer simulations

Overview of ITER TBM program objectives and management

Characterization of a Li₄TiO₄ Tritium Breeder by First-Principles Calculation and an Experimental Approach

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Progress and challenges of the ITER TBM Program from the IO perspective

Cited by 26 publications

References 11 publications

New insights into microstructure of irradiated beryllium based on experiments and computer simulations

New insights into microstructure of irradiated beryllium based on experiments and computer simulations

Overview of ITER TBM program objectives and management

Characterization of a Li4TiO4 Tritium Breeder by First-Principles Calculation and an Experimental Approach

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Characterization of a Li₄TiO₄ Tritium Breeder by First-Principles Calculation and an Experimental Approach