2020
DOI: 10.1016/j.jnucmat.2019.151860
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Material characterization of the VULCANO corium concrete interaction test with concrete representative of Fukushima Daiichi Nuclear Plants

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Cited by 17 publications
(12 citation statements)
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“…New measurements would be needed to form a more definitive understanding. Calculations are performed on: i) well controlled heat treatments of (UO2-ZrO2) / (SiO2-CaO-Al2O3) compositions with two CaO and SiO2 rich concrete compositions [53], and ii) VULCANO corium concrete interaction test VF-U1 with concrete representative of Fukushima Daiichi Nuclear Plants [54].…”
Section: Ex-vessel Coriummentioning
confidence: 99%
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“…New measurements would be needed to form a more definitive understanding. Calculations are performed on: i) well controlled heat treatments of (UO2-ZrO2) / (SiO2-CaO-Al2O3) compositions with two CaO and SiO2 rich concrete compositions [53], and ii) VULCANO corium concrete interaction test VF-U1 with concrete representative of Fukushima Daiichi Nuclear Plants [54].…”
Section: Ex-vessel Coriummentioning
confidence: 99%
“…Al2O3 -6 Fe2O3 in w. %) section under air. The interaction occurred for 15 minutes with an initial temperature of about 2200 K. The microstructure of the solidified corium pool (sample 4 in [54]) is…”
Section: Ex-vessel Coriummentioning
confidence: 99%
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“…It can accumulate at the pedestal bottom and encompass previously present structures [4,24]. Eventually, it can interact with concrete leading to mixing with the basaltic concrete decomposition products: SiO 2 , CaO, MgO,Al 2 O 3 , rebar steel, oxygen (from concrete water content) [19,25,26]. Figure 2b and 2c present some prototypic MCCI debris blocks manufactured in COLIMA [24] and VULCANO facilities [26] with BWR-representative compositions.…”
Section: Estimated Range Of Compositionmentioning
confidence: 99%