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A mesoscale framework for analysis of corrosion induced damage of concrete

Autor: N.P. Pham, Li Yu, Quoc Tri Phung, S. C. Seetharam, F. Druyts, Eric Laloy, Andrey P. Jivkov, B. Kursten

Publikováno v: Seetharam, SC, Laloy, E, Jivkov, A, Yu, L, Phung, QT, Pham, NP, Bruno, K & Druyts, F 2019, ' A mesoscale framework for analysis of corrosion induced damage of concrete ', Construction and Building Materials, vol. 216, pp. 347-361 . https://doi.org/10.1016/j.conbuildmat.2019.04.252

A mesoscale damage framework is developed for investigating the extent of crack or damage penetration in a large-scale concrete component induced by corrosion process under various boundary conditions. The framework synthesizes a robust particle gene

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::28933c72f6314dde246bc67f73948903
https://www.research.manchester.ac.uk/portal/en/publications/a-mesoscale-framework-for-analysis-of-corrosion-induced-damage-of-concrete(ca04aa54-4231-42b8-9a4a-13fa5693f7c5).html

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Review of corrosion studies of metallic barrier in geological disposal conditions with respect to Belgian Supercontainer concept

Autor: F. Druyts, Digby D. Macdonald, N.R. Smart, L. Wang, B. Kursten, E. Weetjens, R. Gens, J. Govaerts

Publikováno v: Corrosion Engineering, Science and Technology. 46:91-97

The Supercontainer design is the preferred option for the underground disposal of high level nuclear waste in Belgium. It consists of a carbon steel overpack surrounded by a thick concrete buffer. In this high alkaline environment and under normal co

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::f6532fd340270f93dee0e57250da3004
https://doi.org/10.1179/1743278210y.0000000022

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The potential presence and minimisation of plutonium within the irradiated beryllium in fusion power plants

Autor: Gilio Cambi, D.G. Cepraga, F. Druyts, V. Massaut, L. Di Pace

Publikováno v: Fusion Engineering and Design. 85:1139-1142

Beryllium is expected to be one of the materials used in DEMO-type fusion power plants as blanket neutron multiplier for solid breeders and also in ITER as protective layer of plasma facing components. Among the aspects to be considered when dealing

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::60c641977d152cbfac2a1bc84e775f66
https://doi.org/10.1016/j.fusengdes.2010.02.026

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Methods for the mitigation of the chemical reactivity of beryllium in steam

Autor: E.C Alves, F Druyts, C.H. Wu

Publikováno v: Journal of Nuclear Materials. :1353-1356

In the safety assessment of future fusion reactors, the reaction of beryllium with steam remains one of the main concerns. In case of a loss of coolant accident (LOCA), the use of beryllium in combination with pressurised water as coolant can lead to

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::c2a497832948296a1a53663943441eff
https://doi.org/10.1016/j.jnucmat.2004.04.204

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Interaction of plasma-facing materials with air and steam

Autor: F. Druyts, C.H. Wu, J. Fays

Publikováno v: Fusion Engineering and Design. :319-325

In the design of ITER-FEAT, several candidate materials are foreseen for plasma-facing components of the divertor (tungsten, carbon fibre-reinforced composites (CFC), molybdenum) and the first wall (beryllium). In the view of accidental scenarios suc

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::7c4102574cdb8053bd43ad438d90b918
https://doi.org/10.1016/s0920-3796(02)00124-2

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Preliminary results of corrosion monitoring studies of carbon steel overpack exposed to supercontainer concrete buffer

Autor: D. De Wilde, G. Nieubourg, Gustavo Duffo, Y. Van Ingelgem, F. Druyts, C. Bataillon, B. Kursten, L. Areias

The supercontainer (SC) is the reference concept for the postconditioning of vitrified high level radioactive waste and spent fuel in Belgium. It is designed with a concrete buffer completely surrounding a carbon steel overpack. A half-scale (HST-2)

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::470b2bfbf2a1dc13f885c57adb47abcb
http://www.tandfonline.com/doi/abs/10.1179/1743278214Y.0000000216

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Review of Passive Corrosion Studies of Carbon Steel in Concrete in the Context of Disposal of HLW and Spent Fuel in Belgium

Autor: N.R. Smart, E. Weetjens, F. Druyts, R. Gens, B. Kursten, J. Govaerts, L. Wang, Digby D. Macdonald

Publikováno v: Volume 1: Low/Intermediate-Level Radioactive Waste Management; Spent Fuel, Fissile Material, Transuranic and High-Level Radioactive Waste Management.

The Supercontainer (SC) design is the preferred option for the final disposal of high level nuclear waste and spent fuel in Belgium. The SC consists of a carbon steel overpack surrounded by a very thick concrete buffer, contained within a stainless s

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::e2f7e69146744d25d56fbffcd8a1ca3a
https://doi.org/10.1115/icem2013-96275

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A new E(E)PROM technology with a TiSi/sub 2/ control gate

Autor: J. Solo, F. Verberne, G. Lemmen, R. Cuppens, F. Druyts, F. Vollebregt

Publikováno v: International Technical Digest on Electron Devices Meeting.

A single polysilicon CMOS process optimized for the production of nonvolatile memory embedded in VLSI logic is described. The process differs from conventional approaches in two aspects: it uses a TiSi/sub 2/ control gate instead of a thicker polysil

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::2943c86eea8c185f2b62085e66f2bd6c
https://doi.org/10.1109/iedm.1989.74354

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