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

https://doi.org/10.1016/j.jnucmat.2019.151860

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

Guvar, 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.