VULCANO VB-U7 experiment on interaction between oxidic corium and hematite-containing concrete

Tuomo Sevon (Corresponding Author), C. Journeau, L. Ferry

Research output: Contribution to journalArticleScientificpeer-review

13 Citations (Scopus)

Abstract

In a severe accident, the core of a reactor melts and forms corium, a mixture that includes molten UO2 and ZrO2. If the reactor pressure vessel fails, corium can interact with concrete.

This paper describes the VB-U7 experiment, which was performed in the VULCANO facility in Cadarache, France, in co-operation between CEA and VTT. This test aims at studying the interaction of more than 50 kg of prototypic oxidic corium with EPR sacrificial ferro-siliceous concrete. The experimental configuration, the measured data and post examination and analysis results are presented.

This test showed that EPR-type ferro-siliceous sacrificial concrete was anisotropically ablated by oxidic corium. This behavior is similar to that of other silica-rich concretes previously tested in CCI and VULCANO facilities. The corium temperature decreased to the value corresponding to about 50 vol% solid fraction when the concrete test section broke, leading to significant spreading.
Original languageEnglish
Pages (from-to)224-229
Number of pages5
JournalAnnals of Nuclear Energy
Volume59
DOIs
Publication statusPublished - 2013
MoE publication typeA1 Journal article-refereed

Fingerprint

Hematite
Concretes
Experiments
Paramagnetic resonance
Pressure vessels
Molten materials
Accidents
Silica
Temperature

Keywords

  • MCCI
  • molten core-concrete interaction
  • severe accident

Cite this

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title = "VULCANO VB-U7 experiment on interaction between oxidic corium and hematite-containing concrete",
abstract = "In a severe accident, the core of a reactor melts and forms corium, a mixture that includes molten UO2 and ZrO2. If the reactor pressure vessel fails, corium can interact with concrete.This paper describes the VB-U7 experiment, which was performed in the VULCANO facility in Cadarache, France, in co-operation between CEA and VTT. This test aims at studying the interaction of more than 50 kg of prototypic oxidic corium with EPR sacrificial ferro-siliceous concrete. The experimental configuration, the measured data and post examination and analysis results are presented.This test showed that EPR-type ferro-siliceous sacrificial concrete was anisotropically ablated by oxidic corium. This behavior is similar to that of other silica-rich concretes previously tested in CCI and VULCANO facilities. The corium temperature decreased to the value corresponding to about 50 vol{\%} solid fraction when the concrete test section broke, leading to significant spreading.",
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VULCANO VB-U7 experiment on interaction between oxidic corium and hematite-containing concrete. / Sevon, Tuomo (Corresponding Author); Journeau, C.; Ferry, L.

In: Annals of Nuclear Energy, Vol. 59, 2013, p. 224-229.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - VULCANO VB-U7 experiment on interaction between oxidic corium and hematite-containing concrete

AU - Sevon, Tuomo

AU - Journeau, C.

AU - Ferry, L.

PY - 2013

Y1 - 2013

N2 - In a severe accident, the core of a reactor melts and forms corium, a mixture that includes molten UO2 and ZrO2. If the reactor pressure vessel fails, corium can interact with concrete.This paper describes the VB-U7 experiment, which was performed in the VULCANO facility in Cadarache, France, in co-operation between CEA and VTT. This test aims at studying the interaction of more than 50 kg of prototypic oxidic corium with EPR sacrificial ferro-siliceous concrete. The experimental configuration, the measured data and post examination and analysis results are presented.This test showed that EPR-type ferro-siliceous sacrificial concrete was anisotropically ablated by oxidic corium. This behavior is similar to that of other silica-rich concretes previously tested in CCI and VULCANO facilities. The corium temperature decreased to the value corresponding to about 50 vol% solid fraction when the concrete test section broke, leading to significant spreading.

AB - In a severe accident, the core of a reactor melts and forms corium, a mixture that includes molten UO2 and ZrO2. If the reactor pressure vessel fails, corium can interact with concrete.This paper describes the VB-U7 experiment, which was performed in the VULCANO facility in Cadarache, France, in co-operation between CEA and VTT. This test aims at studying the interaction of more than 50 kg of prototypic oxidic corium with EPR sacrificial ferro-siliceous concrete. The experimental configuration, the measured data and post examination and analysis results are presented.This test showed that EPR-type ferro-siliceous sacrificial concrete was anisotropically ablated by oxidic corium. This behavior is similar to that of other silica-rich concretes previously tested in CCI and VULCANO facilities. The corium temperature decreased to the value corresponding to about 50 vol% solid fraction when the concrete test section broke, leading to significant spreading.

KW - MCCI

KW - molten core-concrete interaction

KW - severe accident

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DO - 10.1016/j.anucene.2013.04.016

M3 - Article

VL - 59

SP - 224

EP - 229

JO - Annals of Nuclear Energy

JF - Annals of Nuclear Energy

SN - 0306-4549

ER -