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Journal Articles

Material characterization of the VULCANO corium concrete interaction test with concrete representative of Fukushima Daiichi Nuclear Plants

Brissonneau, L.*; Ikeuchi, Hirotomo; Piluso, P.*; Gousseau, J.*; David, C.*; Testud, V.*; Roger, J.*; Bouyer, V.*; Kitagaki, Toru; Nakayoshi, Akira; et al.

Journal of Nuclear Materials, 528, p.151860_1 - 151860_18, 2020/01

 Times Cited Count:18 Percentile:86.64(Materials Science, Multidisciplinary)

Journal Articles

Knowledge obtained from dismantling of large-scale MCCI experiment products for decommissioning of Fukushima Daiichi Nuclear Power Station

Nakayoshi, Akira; Ikeuchi, Hirotomo; Kitagaki, Toru; Washiya, Tadahiro; Bouyer, V.*; Journeau, C.*; Piluso, P.*; Excoffier, E.*; David, C.*; Testud, V.*

Proceedings of International Topical Workshop on Fukushima Decommissioning Research (FDR 2019) (Internet), 4 Pages, 2019/05

Journal Articles

Large scale VULCANO molten core concrete interaction test considering Fukushima Daiichi condition

Bouyer, V.*; Journeau, C.*; Haquet, J. F.*; Piluso, P.*; Nakayoshi, Akira; Ikeuchi, Hirotomo; Washiya, Tadahiro; Kitagaki, Toru

Proceedings of 9th Conference on Severe Accident Research (ERMSAR 2019) (Internet), 13 Pages, 2019/03

Oral presentation

Chemical and microstructural analyses techniques for Fuel Debris simulants and airborne particles

Gu$'e$var, C.*; Faure, J.*; Testud, V.*; Roger, J.*; Domenger, R.*; Valette, R.*; Brackx, E.*; Bouyer, V.*; Journeau, C.*; Berlemont, R.*; et al.

no journal, , 

The URASOL and the DA projects, respectively led by JAEA and CRIEPI in collaboration with ONET/CEA/IRSN, were proposed to obtain basic data on aerosols generation and characteristics from prototypic FD-simulants containing depleted uranium oxide cut by thermal or mechanical processing tools. The whole process developed by ONET/CEA/IRSN allows the manufacturing of specific compositions and supplying corium samples for cutting, the realization of cutting tests and the on-line dedicated aerosols measurements as well as sampling aerosols, to conduct initial FD simulants and aerosols post-trial analyses. This paper focuses on the initial FD simulant and aerosols chemical and microstructural analyses. Results on an ex-vessel composition of FD, named VF-U3, are given.

Oral presentation

First analyses of concrete-corium solids surrogate for the Fukushima Daiichi severe accidents

Brissonneau, L.*; Gousseau, J.*; Piluso, P.*; Bouyer, V.*; Kitagaki, Toru; Ikeuchi, Hirotomo; Yano, Kimihiko; Washiya, Tadahiro

no journal, , 

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