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

Marc Barrachin; Didier Gavillet; Roland Dubourg; Anne   De Bremaecker

doi:10.1016/j.jnucmat.2014.05.079

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

Marc Barrachin, Didier Gavillet, Roland Dubourg, Anne De Bremaecker

Research output › peer-review

Abstract

One objective of the FPT2 test of the PHEBUS FP Program was to study the degradation of an irradiated UO2 fuel test section and the fission product behaviour under conditions of low steam flow. The results of the post-irradiation examinations (PIE) at the upper levels (823 and 900 mm) of the 1-m long test section are presented in this paper. Material interactions leading to local corium formation were identified: firstly between fuel and Zircaloy-4 cladding, notably at 823 mm, where the cladding melting temperature was reached, and secondly between fuel and stainless steel oxides. Regarding fission products, molybdenum left so-called metallic precipitates mainly composed of ruthenium. Xenon and caesium behave similarly whereas barium and molybdenum often seems to be associated in precipitates.

Original language	English
Pages (from-to)	340-354
Number of pages	14
Journal	Journal of Nuclear Materials
Volume	453
Issue number	1-3
DOIs	https://doi.org/10.1016/j.jnucmat.2014.05.079
State	In preparation - 12 Jun 2014

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Cite this

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

abstract = "One objective of the FPT2 test of the PHEBUS FP Program was to study the degradation of an irradiated UO2 fuel test section and the fission product behaviour under conditions of low steam flow. The results of the post-irradiation examinations (PIE) at the upper levels (823 and 900 mm) of the 1-m long test section are presented in this paper. Material interactions leading to local corium formation were identified: firstly between fuel and Zircaloy-4 cladding, notably at 823 mm, where the cladding melting temperature was reached, and secondly between fuel and stainless steel oxides. Regarding fission products, molybdenum left so-called metallic precipitates mainly composed of ruthenium. Xenon and caesium behave similarly whereas barium and molybdenum often seems to be associated in precipitates.",

keywords = "Phebus, FPT2, Fission products, Severe accident, Core degradation",

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AB - One objective of the FPT2 test of the PHEBUS FP Program was to study the degradation of an irradiated UO2 fuel test section and the fission product behaviour under conditions of low steam flow. The results of the post-irradiation examinations (PIE) at the upper levels (823 and 900 mm) of the 1-m long test section are presented in this paper. Material interactions leading to local corium formation were identified: firstly between fuel and Zircaloy-4 cladding, notably at 823 mm, where the cladding melting temperature was reached, and secondly between fuel and stainless steel oxides. Regarding fission products, molybdenum left so-called metallic precipitates mainly composed of ruthenium. Xenon and caesium behave similarly whereas barium and molybdenum often seems to be associated in precipitates.

KW - Phebus

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KW - Fission products

KW - Severe accident

KW - Core degradation

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