Fission products and nuclear fuel behaviour under severe accident conditions part 2: Fuel behaviour in the VERDON-1 sample

JOURNAL OF NUCLEAR MATERIALS

卷:495

Article

Geiger, E.^1,2  Le Gall, C.¹  Gallais-During, A.¹  Pontillon, Y.¹  Lamontagne, J.¹  Hanus, E.¹  Ducros, G.¹ 

[1] CEA, DEN, DEC, F-13108 St Paul Les Durance, France

[2] Royal Mil Coll Canada, Dept Chem & Chem Engn, 11 Gen Crerar Crescent, Kingston, ON K7K 7B4, Canada

关键词: UO2 irradiated fuel;    Fuel behaviour;    LWR;    Severe accident;    VERDON tests;    Post-test characterisations;    Fuel-cladding interactions;   

DOI  :  10.1016/j.jnucmat.2017.08.002

来源: Elsevier

【 摘 要 】

Within the framework of the International Source Term Programme (ISTP), the VERDON programme aims at quantifying the source term of radioactive materials in case of a hypothetical severe accident in a light water reactor (LWR). Tests were performed in a new experimental laboratory (VERDON) built in the LECA-STAR facility (CEA Cadarache). The VERDON-1 test was devoted to the study of a high burn-up UO2 fuel and FP releases at very high temperature (approximate to 2873 K) in a reducing atmosphere. Post-test qualitative and quantitative characterisations of the VERDON-1 sample led to the proposal of a scenario explaining the phenomena occurring during the experimental sequence. Hence, the fuel and the cladding may have interacted which led to the melting of UO2-ZrO2 alloy. Although no relocation was observed during the test, it may have been imminent. (C) 2017 Elsevier B.V. All rights reserved.

【 授权许可】

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