Examination of melted fuel rods and released core material from the first Phebus-FP reactor accident experiment

Bottomley, D.; Stalios, A.D.; Glatz, Jean‐Paul; Sätmark, B; Walker, C.T.

doi:10.1016/s0022-3115(99)00257-3

Cited by 17 publications

(5 citation statements)

References 10 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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“…This is confirmed by post-test examinations of the solidified debris (Bottomley et al, 2000), which reveal the presence of steel components (Fe, Cr, Ni) and their oxides. The composition and microstructure are similar to those of TMI-2 corium samples.…”

Section: Bundle Degradationmentioning

confidence: 52%

Phébus-FP: Results and significance for plant safety in Switzerland

Birchley

Haste

Bruchertseifer

et al. 2005

Nuclear Engineering and Design

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“…Representative integral tests are STEP [16], ACRR-ST [17], PBF-SFD [18], LOFT-FP [19] and Phebus-FP [20][21][22][23] tests. The single-effect tests for the evaluation of FP and actinide release behaviour are ORNL HI/VI [24], HEVA/VERCORS [25][26][27] and VEGA [28][29][30] tests.…”

Section: Fp and Actinide Release Experimentsmentioning

confidence: 99%

“…It was found in the LOFT-FP tests that Cs compounds were deposited as the water soluble forms [19]. In Phebus-FP tests, more detailed information of the core degradation behaviour, the FP transport behaviour in the reactor cooling system and the containment vessel was evaluated [20][21][22][23]. Gaseous iodine as well as aerosol iodine were generated in the reactor coolant system and the containment vessel, and their amounts were increased by the presence of B 4 C moderator [35].…”

Section: Fp and Actinide Release Experimentsmentioning

confidence: 99%

Research Program for the Evaluation of Fission Product and Actinide Release Behaviour, Focusing on their Chemical Forms

et al. 2015

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We have launched a new research program for evaluation of fission product and actinide release behaviour under severe accident conditions, focusing on their chemical forms. In this research program, the fission product and actinide release models incorporated in the severe accident analysis code will be improved by implementing effects of chemical forms that are to be obtained by an experimental investigation on the fission product and actinide release behaviour from irradiated fuels. A novel insitu measurement method of chemical forms of fission products and actinides just after their release as well as an off-line analysis method will be employed as the experimental means for evaluating the chemical forms at the release and their stability after release.

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Examination of melted fuel rods and released core material from the first Phebus-FP reactor accident experiment

Cited by 17 publications

References 10 publications

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

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

Phébus-FP: Results and significance for plant safety in Switzerland

Research Program for the Evaluation of Fission Product and Actinide Release Behaviour, Focusing on their Chemical Forms

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