Modelling pellet-clad mechanical interaction during extended reduced power operation in bonded nuclear fuel

Haynes, T.A.; Ball, J.A.; Shea, J.H.; Wenman, M.R.

doi:10.1016/j.jnucmat.2015.05.021

Cited by 11 publications

(3 citation statements)

References 33 publications

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“…If the buffer and kernel are de-bonded, as has been assumed elsewhere [76] , the stress concentration in the kernel might not be as large and so the crack might not 'jump' from one material to the other. This in turn, might reduce the stress concentration in the SiC, again analogous to the situation observed in conventional pellet-clad interaction [77] . We are currently working to implement both residual stress and irradiation-induced shrinkage in our model.…”

Section: Kernel-ipyc Interfacementioning

confidence: 65%

Peridynamic Modelling of Cracking in TRISO Particles for High Temperature Reactors

Haynes¹,

Battistini²,

Leide³

et al. 2023

Preprint

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A linear-elastic computer simulation (model) for a single particle of TRISO fuel has been built using a bond-based peridynamic technique implemented in the finite element code 'Abaqus'. The model is able to consider the elastic and thermal strains in each layer of the particle and to simulate potential fracture both within and between layers. The 2D cylindrical model makes use of a plane stress approximation perpendicular to the plane modelled. The choice of plane stress was made by comparison of 2D and 3D finite element models. During an idealised ramp to normal operating power for a kernel of 0.267 W and a bulk fuel temperature of 1305 K, cracks initiate in the buffer near to the kernel-buffer interface and propagate towards the buffer-iPyC coating interface, but do not penetrate the iPyC and containment of the fission products is maintained. In extreme accident conditions, at around 600% (1.60 W) power during a power ramp at 100% power (0.267 W) per second, cracks were predicted to form on the kernel side of the kernel-buffer interface, opposite existing cracks in the buffer. These were predicted to then only grow further with further increases in power. The SiC coating was predicted to subsequently fail at a power of 940% (2.51 W), with cracks formed rapidly at the iPyC-SiC interface and propagating in both directions. These would overcome the containment to fission gas release offered by the SiC 'pressure vessel'. The extremely high power at which failure was predicted indicates the potential safety benefits of the proposed high temperature reactor design based on TRISO fuel.

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Section: Kernel-ipyc Interfacementioning

confidence: 65%

Peridynamic Modelling of Cracking in TRISO Particles for High Temperature Reactors

Haynes¹,

Battistini²,

Leide³

et al. 2023

Preprint

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show abstract

“…At the end of the ramp, the crack width was 10.9 µm at position γ, this is greater than the 8.3 µm in the uniform un-deposited 'cold' model and 6.5 µm in the uniformly deposited 'hot' model. The crack width at the bore, shown in Whilst displacements of a magnitude of 5-10 µm might at first sight appear trivial, previous work [6] has shown the importance upon the stress state of pellet fragment displacement of this order. The key difference between a manufacturing tolerance and these displacements is that they are applied during PCMI and after the fuel has been 'conditioned'.…”

Section: Azimuthal Motion Of Pellet Fragmentsmentioning

confidence: 91%

“…This paper investigates the hypothesis that it is the higher temperature that impacts PCMI and not the temperature difference. The effect of the temperature profile was modelled using the PELICAN (r-θ) coupled temperature-displacement finite element model recently developed at Imperial College London for the AGR system [6], [24][25]. PELICAN is a development of Mella and Wenman's (r-z) axisymmetric model [26] and is able to model the r-θ plane of nuclear fuel.…”

Section: Modelling Agr Fuel Performancementioning

confidence: 99%