Výsledky vyhledávání - "tritium retention"

Akademický článek

3D benchmark experiments of tritium in tungsten for tritium measurements by detecting β-ray induced X-rays

Autor: Yang Yang, Zhilin Chen, Po Huang, Yong Yang, Caifeng Lai, Wenxiang Jiang

Publikováno v: Nuclear Materials and Energy, Vol 39, Iss , Pp 101635- (2024)

Tungsten is one of the most promising materials for plasma facing components (PFCs), and β-ray induced X-ray spectrometry (BIXS) is an important non-destructive method to obtain tritium depth profile and retention information for the development of

Externí odkaz: https://doaj.org/article/3bdc713dff3144a5a799400216b723b9

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Akademický článek

Influence of helium bubbles location on hydrogen isotope retention and exchange behavior in plasma-facing materials: A numerical simulation investigation

Autor: Y.J. Huang, C. Hao, Q.H. Liu, J.P. Zhu, F. Sun, Y. Oya, Y.C. Wu

Publikováno v: Nuclear Materials and Energy, Vol 38, Iss , Pp 101596- (2024)

Tritium (T) is a costly radioactive element that, when retained in plasma-facing materials (PFMs), not only results in fuel loss but also raises issues of radioactive contamination. Hydrogen isotope exchange is a potential method for T removal in fut

Externí odkaz: https://doaj.org/article/4eaf2e4376c24a838dd621efc4b814c9

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Akademický článek

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Akademický článek

Studies on the impacts of the pore size and shape on deuterium retention in tungsten fuzzy nanostructures

Autor: J.Y. Chen, S.Y. Dai, K.R. Yang, C.R. Zu, D.P. Liu, W.Y. Ni, S.G. Liu

Publikováno v: Nuclear Fusion, Vol 64, Iss 5, p 056006 (2024)

Tritium retention in plasma-facing materials is a critical issue that can significantly impact the long-term and steady-state operation of fusion devices. The experiments conducted in the laboratory device MIES have confirmed that the presence of the

Externí odkaz: https://doaj.org/article/c7aa23d8b30f4ffb8af6f1909b63fc15

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Akademický článek

Reassessment of tritium content in CFC tiles exposed to the JET D-T campaign in 1997

Autor: J. Likonen, N. Bekris, J.P. Coad, C. Ayres, N. Gotts, I. Jepu, Y. Zayachuk, A. Widdowson, I. Wilson, N. Catarino, E. de Alves

Publikováno v: Nuclear Materials and Energy, Vol 33, Iss , Pp 101312- (2022)

In 2019 two MkIIA divertor tiles (6IN3 and 4BN4) exposed during DTE1 were retrieved at CCFE for Thermal Desorption Spectroscopy (TDS) and pyrolysis analyses. A set of samples were prepared using a coring technique. The highest tritium (T) inventories

Externí odkaz: https://doaj.org/article/a9ed19be133e433ba32a3be786abcf27

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Interaction of primary precipitates in reduced -activation ferritic/martensitic steel F82H with hydrogen atoms: Atomistic calculation based on the density functional theory

Autor: Hirotomo Iwakiri, Yoshiyuki Watanabe, Koichi Sato, Daiji Kato

Publikováno v: Nuclear Materials and Energy, Vol 31, Iss , Pp 101157- (2022)

To understand the interaction of hydrogen isotopes with VC and Cr23C6 precipitates, in reduced-activation ferritic/martensitic steel (F82H), we have performed first-principles calculations based on density functional theory. Energy calculations and e

Externí odkaz: https://doaj.org/article/bd41463349e94bb0a7395fe33475d4ee

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Akademický článek

Tritium removal from JET-ILW after T and D–T experimental campaigns

Publikováno v: Nuclear Fusion, Vol 63, Iss 11, p 112014 (2023)

After the second Deuterium–Tritium Campaign (DTE2) in the JET tokamak with the ITER-Like Wall (ILW) and full tritium campaigns that preceded and followed after the DTE2, a sequence of fuel recovery methods was applied to promote tritium removal fro

Externí odkaz: https://doaj.org/article/d69d3fdfcb534f74bb1a597f19096b2b

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Akademický článek

Tritium distributions in castellated structures of Be limiter tiles from JET-ITER-like wall experiments

Autor: S. Lee, Y. Hatano, S. Masuzaki, Y. Oya, M. Tokitani, M. Yajima, T. Otsuka, N. Ashikawa, Y. Torikai, N. Asakura, H. Nakamura, H. Kurotaki, T. Hayashi, T. Nozawa, A.M. Ito, J. Likonen, A. Widdowson, M. Rubel, JET Contributors

Publikováno v: Nuclear Fusion, Vol 63, Iss 4, p 046023 (2023)

Tritium retention in the castellated structure of beryllium limiters used in JET with the ITER-like wall (ILW) during the first (ILW1), third (ILW3) and all three (ILW1-3) campaigns were examined and evaluated. Tritium was deposited on the surfaces i

Externí odkaz: https://doaj.org/article/d0d5edb2e9684b5397b2ce67a7bb9c40

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