Mechanical performance of SiC three-layer cladding in PWRs

Avincola, Valentina Angelici; Guenoun, Pierre; Shirvan, Koroush

doi:10.1016/j.nucengdes.2016.10.008

Cited by 29 publications

(6 citation statements)

References 20 publications

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“…As an example, Stone et al give a hoop stress of +10 MPa on the inner surface and -180 MPa on the outer surface at the end of the first power cycle; during the shut-down, the hoop stress increases to +190 and -125 MPa respectively [32]. One of the key challenges to the use of an internal monolith is its structural integrity under these tensile stresses [14,33]. Outer monoliths are expected to remain in compression and therefore not lose their integrity [14,32].…”

Section: Modelling Sic/sic Cladding Performancementioning

confidence: 99%

“…In addition, there is evidence that Young's modulus decreases by around 20% during the expected lifetime of SiC/SiC LWR fuel [37]. For simplicity and following the lead of Avincola et al [33], the elastic modulus of the monolith was set to twice that of the composite i.e. 564 GPa; the sensitivity to this assumption is discussed in Section 3.5, as well as the sensitivity study in Section 3.8.3.…”

Section: Elastic Modulusmentioning

confidence: 99%

“…During unloading, any elastic strains are removed; fibre pull out, modelled as plastic strain, is assumed to be a permanent deformation and the strain remains; any trusses that have failed remain with a negligibly small elastic modulus. For regions with no fibres such as the monoliths, no fibre pull-out was accrued and the Young's modulus was doubled [33]. In order to prevent unphysical crack patterns, material within 5 nodal spaces (80 µm) of the left or right hand edges was not permitted to fail.…”

Section: Composite Fracture Modelmentioning

confidence: 99%

“…Finally, Figure 17 shows the sensitivity of the crack pattern and time to failure for simulations with an internal monolith and different elastic moduli for the monolith. The elastic modulus assumed in this work was set to twice that of the composite, following the lead of Angelici et al [33] . The elastic modulus of the composite was chosen so that the complete elastic and fracture response described by Jacobsen et al could be applied to the composite [35].…”

Section: Monolith Elastic Modulusmentioning

confidence: 99%

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Preliminary modelling of crack nucleation and propagation in SiC/SiC accident-tolerant fuel during routine operational transients using peridynamics

Haynes

Shepherd

Wenman

2020

Journal of Nuclear Materials

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Silicon carbide fibre in silicon carbide matrix composites (SiC/SiC) are a promising cladding for use in accident tolerant fuels (ATF) in current light water reactor (LWR) designs. However, as they are a radically different material from current metal clads, current thermomechanical simulation methods struggle to accurately predict their behaviour, especially regarding the potential development of cracks. Thus, a new peridynamic model for SiC/SiC cladding has been developed in the Abaqus finite element code. The material model was isotropic and considers matrix cracking and fibre pull-out. The thermal expansion, swelling and the degradation of the thermal conductivity are modelled under typical LWR irradiation conditions. The swelling on the outer surface is predicted to be greater than the inner surface due to the lower irradiation temperature, causing a tensile stress on the inside of the cladding; tension being more challenging for a ceramic than a metal. This stress increases during the decrease in power at the start of a typical pressurised water reactor refuelling outage and causes microcracking of the matrix on the cladding inner surface. In models without fibres, cracks would propagate through the cladding. If fibres are modelled, matrix cracking will extend to a depth of around 20% through the cladding from the inner surface, which is unlikely to be an acceptable design. If an inner monolith of SiC is additionally modelled, cracking propagates through the monolith and acts as a stress raiser for matrix cracking in the composite, and therefore does not constitute a design improvement. If an outer SiC monolith is modelled, fibre pull-out strain on the inner surface of the cladding was increased by just under 70%. No cracks are predicted in an outer monolith which may therefore remain gas-tight and thus a more suitable design. These predictions are consistent with experimental findings. Highlights• Irradiation of accident tolerant SiC/SiC cladding is modelled using peridynamics.• Due to swelling, a tensile stress is predicted on the inside of the cladding. • In the absence of a monolith, micro-cracking extends to 20% from the inner surface.• Cracks in an inner monolith are a stress raiser in the composite.• No cracks are predicted in an outer monolith, hence it's the most promising design.

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Section: Modelling Sic/sic Cladding Performancementioning

confidence: 99%

Section: Elastic Modulusmentioning

confidence: 99%

Section: Composite Fracture Modelmentioning

confidence: 99%

Section: Monolith Elastic Modulusmentioning

confidence: 99%

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Preliminary modelling of crack nucleation and propagation in SiC/SiC accident-tolerant fuel during routine operational transients using peridynamics

Haynes

Shepherd

Wenman

2020

Journal of Nuclear Materials

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“…Previously done thermomechanical analysis on the multilayer SiC concept [18] showed more suitable results in fresh state during Reactivity Initiated Accident (RIA) than zircaloy cladding. An upgradation of this concept includes a triplex SiC cladding model [19], and an addition of an Environmental Barrier Coating (EBC) on the outer SiC CMC layer [20] SiC has been well researched as a possible cladding concept based on its material properties. Furthermore, a safety evaluation is necessary in simulated transient conditions to be used as an ATF.…”

Section: Introductionmentioning

confidence: 99%

Simulation of Zircaloy and SiC cladding thermal performance of a nuclear fuel rod subassembly

Handa¹,

Ray²,

Munshi³

et al. 2022

Eng. Res. Express

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A thermal-hydraulic analysis of a nuclear fuel rod subassembly of a Pressurized Water Reactor (PWR) has been performed during a Loss of Flow Accident (LOFA). Two different cladding materials are studied in this exercise namely, (a) conventional Zircaloy (Zr) and (b) a Silicon Carbide (SiC) cladding concept approach using monolithic SiC and SiC composite two-layer structure. The simulation is carried out by using USNRC licensed and AERB approved RELAP5/MOD3.4 code. A short-time problem is analyzed, neglecting the burnup change and irradiation effects. A transition into film boiling is observed in the upper part of the rod during LOFA, causing the convective heat transfer coefficient to decrease. The peak cladding temperatures and the Critical Heat Flux Ratio (CHFR) values of the two cladding materials are compared. From a safety perspective, the use of SiC is considered as it will be able to maintain performance during the operational transients.

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Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings

Wagih

Spencer

Hales

et al. 2018

Annals of Nuclear Energy

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Mechanical performance of SiC three-layer cladding in PWRs

Cited by 29 publications

References 20 publications

Preliminary modelling of crack nucleation and propagation in SiC/SiC accident-tolerant fuel during routine operational transients using peridynamics

Preliminary modelling of crack nucleation and propagation in SiC/SiC accident-tolerant fuel during routine operational transients using peridynamics

Simulation of Zircaloy and SiC cladding thermal performance of a nuclear fuel rod subassembly

Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings

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