Fuel and fission product behaviour in early phases of a severe accident. Part I: Experimental results of the PHEBUS FPT2 test

Barrachin, M.; Gavillet, D.; Dubourg, R.; Bremaecker, A. De

doi:10.1016/j.jnucmat.2014.05.079

Cited by 17 publications

(12 citation statements)

References 27 publications

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“…This would suggest that the zirconium is in excess. However, the elemental U/Zr ratios of real irradiated corium samples from and above the central pool analysed in the degraded FPT0, 1 and 2 bundles of the Phébus PF project [22][23][24][25][26][27][28] as well as in the TMI-2 samples [29] for a solidified fully oxidized corium are notably higher. These values ranged between 1.0 and 1.18 and are shown in Figure 12.…”

Section: Discussionmentioning

confidence: 99%

Investigations of the melting behaviour of the U–Zr–Fe–O system

Bottomley

Murray-Farthing

Manara

et al. 2015

Journal of Nuclear Science and Technology

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During a severe nuclear accident, the UO 2 fuel rods, Zircaloy cladding, guide tubes, absorber and steel structural components inside the reactor pressure vessel overheat and a series of interactions between these elements and the steam atmosphere occur. These produce more heat in addition to the decay heat and result in a liquid corium of oxidic and metallic phases depending on the exact conditions and processes. A major systems resulting from this is the U-Zr-Fe-O system. High-temperature data for this system is important in order to be able to model these interactions. The Joint Research Centre, Institute for Transuranium Elements (JRC-ITU) has been examining the melting ranges for this system over the whole FeO range by means of a specialized laser flash technique that achieves very high temperatures and avoids crucible contamination. The melted zones were examined for their structure, composition and for estimation of the liquidus and solidus temperatures. The results showed that with FeO contents of over 20mol% there was a very large melting range that would permit long liquid cooling times and extend the relocation of fuel material within the reactor pressure vessel. Based on these results, the main phase regimes expected under severe accident conditions could be identified.

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Section: Discussionmentioning

confidence: 99%

Investigations of the melting behaviour of the U–Zr–Fe–O system

Bottomley

Murray-Farthing

Manara

et al. 2015

Journal of Nuclear Science and Technology

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“…found a eutectic between FeO and UO 2 at 1610 K (1337°C) [31]. In discussion of the PHEBUS tests [32], it was noted the potential for FeO x to interact with UO 2 . Previous separate effects tests using a UO 2 crucible loaded with FeO powder, experience rapid penetration of the FeO into the UO 2 under the 1673 K (1400°C) inert atmosphere test conditions [33].…”

Section: Fuel Degradation and Relocation Characteristicsmentioning

confidence: 99%

Severe Accident Analysis Of BWR Core Fueled With UO<sub>2</sub>/FeCrAl with Updated Materials and Melt Properties From Experiments

Robb¹,

McMurray²,

Terrani³

2016

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“…Bechta et al found a eutectic between FeO and UO 2 at 1,610 K (1,337°C) [21]. In discussion of the PHEBUS tests [22], the potential for FeO x to interact with UO 2 was noted. Previous separate effects tests that used a UO 2 crucible loaded with FeO powder experienced rapid penetration of the FeO into the UO 2 under the 1,673 K (1,400°C) inert atmosphere test conditions [23].…”

Section: Eutecticsmentioning

confidence: 97%