Fission product release in the first two PHEBUS tests FPT0 and FPT1

Dubourg, R.; Faure-Geors, H.; Nicaise, G.; Barrachin, M.

doi:10.1016/j.nucengdes.2005.03.007

Cited by 46 publications

(14 citation statements)

References 39 publications

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“…(left) Micrography of irradiated UO 2 (33 GW j/T) after heat treatment at 2000 K during 3 h(Dubourg et al, 2005). (right) Swelling of UO 2 during an accident.…”

mentioning

confidence: 99%

Porous materials with two populations of voids under internal pressure: I. Instantaneous constitutive relations

Vincent

Monerie

Suquet

2009

International Journal of Solids and Structures

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International audienceThis study is devoted to the mechanical behavior of uranium dioxide (UO2) which is a porous material with two populations of voids of very different size subjected to internal pressure. The smallest voids are intragranular and spherical in shape whereas the largest pores located at the grain boundary are ellipsoidal and randomly oriented. In this first part of the study, attention is focused on the effective properties of these materials with fixed microstructure. In a first step the poroelastic properties of these doubly voided materials are studied. Then two rigorous upper bounds are derived for the effective poro-plastic constitutive relations of these materials. The first bound, obtained by generalizing the approach of Gologanu et al. (1994) to compressible materials, is accurate at high stress-triaxiality. The second one, which derives from the variational method of Ponte Casta˜neda (1991), is accurate when the stress triaxiality is low. A N-phase model, inspired by Bilger et al. (2002), is proposed which matches the best of the two bounds at low and high triaxiality. The effect of internal pressures is discussed. In particular it is shown that when the two internal pressures coincide, the effective flow surface of the saturated biporous material is obtained from that of the drained material by a shift along the hydrostatic axis. However, when the two pressures are different, the modifications brought to the effective flow surface in the drained case involve not only a shift along the hydrostatic axis but also a change in shape and size of the surface

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“…(left) Micrography of irradiated UO 2 (33 GW j/T) after heat treatment at 2000 K during 3 h(Dubourg et al, 2005). (right) Swelling of UO 2 during an accident.…”

mentioning

confidence: 99%

Porous materials with two populations of voids under internal pressure: I. Instantaneous constitutive relations

Vincent

Monerie

Suquet

2009

International Journal of Solids and Structures

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“…This facility therefore offers several advantages, compared to the other in-pile facilities in Table 1, which include: a complete integral design (including a simulated primary circuit and containment vessel); complete instrumentation to assess the temporal and spatial progression of the core melt sequence, including on-line and sequential sampling of solid, liquid and gaseous effluents at various points in the experimental train (e.g., fission product, aerosol and iodine speciation sampling); the possibility of conducting the experiment over extended periods of time (at high temperature); and complete pre and post-test examination (including gamma scanning, and transmission and emission tomography). The data obtained from this program, as well as the out-of-pile Vercors program, have been extensively used for verification of codes for source term analyses [25,27,[51][52][53].…”

Section: Review Of Melt Progression and Fission Product Release Expermentioning

confidence: 99%

Overview of experimental programs on core melt progression and fission product release behaviour

Lewis

Dickson

Iglesias

et al. 2008

Journal of Nuclear Materials

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“…They indicate that the oxygen/metal ratio would be about 2.11. According to a second calculation [43,44] taking into account both oxygen surface exchange and volume diffusion, i.e. using a kinetic rather a thermodynamic approach, the oxygen/ metal ratio in fuel would be about 2.08 at 600 mm for a maximum temperature of 2600 K. For comparison, the deviations of fuel stoichiometry were about 2.14 for samples obtained from the molten core of the Three Mile Island Unit 2 (TMI-2) reactor [45] where the total pressure was higher than during the PHEBUS FP tests.…”

Section: Post-test Examinationsmentioning

confidence: 99%

New modelling of the U–O–Zr phase diagram in the hyper-stoichiometric region and consequences for the fuel rod liquefaction in oxidising conditions

Barrachin

Chevalier

Cheynet

et al. 2008

Journal of Nuclear Materials

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Fission product release in the first two PHEBUS tests FPT0 and FPT1

Cited by 46 publications

References 39 publications

Porous materials with two populations of voids under internal pressure: I. Instantaneous constitutive relations

Porous materials with two populations of voids under internal pressure: I. Instantaneous constitutive relations

Overview of experimental programs on core melt progression and fission product release behaviour

New modelling of the U–O–Zr phase diagram in the hyper-stoichiometric region and consequences for the fuel rod liquefaction in oxidising conditions

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