Abstract
This paper investigates the residual stresses and interfacial shear strength of a TiAlN coating on Zr-Nb-Sn-Fe alloy (ZIRLO™) substrate designed to improve corrosion resistance of fuel cladding used in water-cooled nuclear reactors, both during normal and exceptional conditions, e.g. a loss of coolant event (LOCA). The distribution and maximum value of the interfacial shear strength has been estimated using a modified shear-lag model. The parameters critical to this analysis were determined experimentally. From these input parameters the interfacial shear strength between the TiAlN coating and ZIRLO™ substrate was inferred to be around 120 MPa. It is worth noting that the apparent strength of the coating is high (∼3.4 GPa). However, this is predominantly due to the large compressive residuals stress (3 GPa in compression), which must be overcome for the coating to fail in tension, which happens at a load just 150 MPa in excess of this.
| Original language | English (US) |
|---|---|
| Pages (from-to) | 718-727 |
| Number of pages | 10 |
| Journal | Journal of Nuclear Materials |
| Volume | 466 |
| DOIs | |
| State | Published - Mar 1 2015 |
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All Science Journal Classification (ASJC) codes
- Nuclear and High Energy Physics
- Materials Science(all)
- Nuclear Energy and Engineering
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Evaluation of the interfacial shear strength and residual stress of TiAlN coating on ZIRLO™ fuel cladding using a modified shear-lag model approach. / Liu, Y.; Bhamji, I.; Withers, P. J.; Wolfe, Douglas Edward; Motta, Arthur Thompson; Preuss, M.
In: Journal of Nuclear Materials, Vol. 466, 01.03.2015, p. 718-727.Research output: Contribution to journal › Article
TY - JOUR
T1 - Evaluation of the interfacial shear strength and residual stress of TiAlN coating on ZIRLO™ fuel cladding using a modified shear-lag model approach
AU - Liu, Y.
AU - Bhamji, I.
AU - Withers, P. J.
AU - Wolfe, Douglas Edward
AU - Motta, Arthur Thompson
AU - Preuss, M.
PY - 2015/3/1
Y1 - 2015/3/1
N2 - This paper investigates the residual stresses and interfacial shear strength of a TiAlN coating on Zr-Nb-Sn-Fe alloy (ZIRLO™) substrate designed to improve corrosion resistance of fuel cladding used in water-cooled nuclear reactors, both during normal and exceptional conditions, e.g. a loss of coolant event (LOCA). The distribution and maximum value of the interfacial shear strength has been estimated using a modified shear-lag model. The parameters critical to this analysis were determined experimentally. From these input parameters the interfacial shear strength between the TiAlN coating and ZIRLO™ substrate was inferred to be around 120 MPa. It is worth noting that the apparent strength of the coating is high (∼3.4 GPa). However, this is predominantly due to the large compressive residuals stress (3 GPa in compression), which must be overcome for the coating to fail in tension, which happens at a load just 150 MPa in excess of this.
AB - This paper investigates the residual stresses and interfacial shear strength of a TiAlN coating on Zr-Nb-Sn-Fe alloy (ZIRLO™) substrate designed to improve corrosion resistance of fuel cladding used in water-cooled nuclear reactors, both during normal and exceptional conditions, e.g. a loss of coolant event (LOCA). The distribution and maximum value of the interfacial shear strength has been estimated using a modified shear-lag model. The parameters critical to this analysis were determined experimentally. From these input parameters the interfacial shear strength between the TiAlN coating and ZIRLO™ substrate was inferred to be around 120 MPa. It is worth noting that the apparent strength of the coating is high (∼3.4 GPa). However, this is predominantly due to the large compressive residuals stress (3 GPa in compression), which must be overcome for the coating to fail in tension, which happens at a load just 150 MPa in excess of this.
UR - http://www.scopus.com/inward/record.url?scp=84955670698&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=84955670698&partnerID=8YFLogxK
U2 - 10.1016/j.jnucmat.2015.06.003
DO - 10.1016/j.jnucmat.2015.06.003
M3 - Article
AN - SCOPUS:84955670698
VL - 466
SP - 718
EP - 727
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
SN - 0022-3115
ER -