Discrete element method study of fuel relocation and dispersal during loss-of-coolant accidents

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Discrete element method study of fuel relocation and dispersal during loss-of-coolant accidents. / Govers, Kevin; Verwerft, Marc.

In: Journal of Nuclear Materials, Vol. 478, 26.05.2016, p. 322-332.

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@article{3cca69ee46ec4ee1928abee5e90585e2,
title = "Discrete element method study of fuel relocation and dispersal during loss-of-coolant accidents",
abstract = "The fuel fragmentation, relocation and dispersal (FFRD) during LOCA transients today retain the attention of the nuclear safety community. The fine fragmentation observed at high burnup may, indeed, affect the Emergency Core Cooling System performance: accumulation of fuel debris in the cladding ballooned zone leads to a redistribution of the temperature profile, while dispersal of debris might lead to coolant blockage or to debris circulation through the primary circuit. This work presents a contribution, by discrete element method, towards a mechanistic description of the various stages of FFRD. The fuel fragments are described as a set of interacting particles, behaving as a granular medium. The model shows qualitative and quantitative agreement with experimental observations, such as the packing efficiency in the balloon, which is shown to stabilize at about 55%. The model is then applied to study fuel dispersal, for which experimental parametric studies are both difficult and expensive.",
keywords = "study, fuel relocation, Dispersal, loss of coolant, accidents",
author = "Kevin Govers and Marc Verwerft",
note = "SCORE=10",
year = "2016",
month = may,
day = "26",
doi = "10.1016/j.jnucmat.2016.05.031",
language = "English",
volume = "478",
pages = "322--332",
journal = "Journal of Nuclear Materials",
issn = "0022-3115",
publisher = "Elsevier",

}

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TY - JOUR

T1 - Discrete element method study of fuel relocation and dispersal during loss-of-coolant accidents

AU - Govers, Kevin

AU - Verwerft, Marc

N1 - SCORE=10

PY - 2016/5/26

Y1 - 2016/5/26

N2 - The fuel fragmentation, relocation and dispersal (FFRD) during LOCA transients today retain the attention of the nuclear safety community. The fine fragmentation observed at high burnup may, indeed, affect the Emergency Core Cooling System performance: accumulation of fuel debris in the cladding ballooned zone leads to a redistribution of the temperature profile, while dispersal of debris might lead to coolant blockage or to debris circulation through the primary circuit. This work presents a contribution, by discrete element method, towards a mechanistic description of the various stages of FFRD. The fuel fragments are described as a set of interacting particles, behaving as a granular medium. The model shows qualitative and quantitative agreement with experimental observations, such as the packing efficiency in the balloon, which is shown to stabilize at about 55%. The model is then applied to study fuel dispersal, for which experimental parametric studies are both difficult and expensive.

AB - The fuel fragmentation, relocation and dispersal (FFRD) during LOCA transients today retain the attention of the nuclear safety community. The fine fragmentation observed at high burnup may, indeed, affect the Emergency Core Cooling System performance: accumulation of fuel debris in the cladding ballooned zone leads to a redistribution of the temperature profile, while dispersal of debris might lead to coolant blockage or to debris circulation through the primary circuit. This work presents a contribution, by discrete element method, towards a mechanistic description of the various stages of FFRD. The fuel fragments are described as a set of interacting particles, behaving as a granular medium. The model shows qualitative and quantitative agreement with experimental observations, such as the packing efficiency in the balloon, which is shown to stabilize at about 55%. The model is then applied to study fuel dispersal, for which experimental parametric studies are both difficult and expensive.

KW - study

KW - fuel relocation

KW - Dispersal

KW - loss of coolant

KW - accidents

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/21593268

U2 - 10.1016/j.jnucmat.2016.05.031

DO - 10.1016/j.jnucmat.2016.05.031

M3 - Article

VL - 478

SP - 322

EP - 332

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

SN - 0022-3115

ER -

ID: 2061064