Review on chromium coated zirconium alloy accident tolerant fuel cladding

J Yang, M Steinbrück, C Tang, M Große, J Liu… - Journal of Alloys and …, 2022‏ - Elsevier
Abstract The Fukushima-Daiichi accident revealed that the zirconium fuel claddings have
the significant safety risk of hydrogen detonation due to the strong oxidation and hydrogen …

Characterization of distribution of residual stress in shot-peened layer of nickel-based single crystal superalloy DD6 by nanoindentation technique

M Liu, Q Zheng, X Wang, C Xu - Mechanics of Materials, 2022‏ - Elsevier
Hardness, elastic modulus, yield strength, work hardening exponent, and residual stress
within shot-peened layer of nickel-based single crystal superalloy DD6 were experimentally …

Effect of Cr coating on the mechanical integrity of Accident Tolerant Fuel cladding under ring compression test

J Kim, SH Joung, Y Lee - Journal of Nuclear Materials, 2023‏ - Elsevier
The mechanical behavior of Cr-coated Zr-Nb alloy cladding was investigated with Ring
Compression Test (RCT) and Finite Element Analysis (FEA). The post-RCT specimens were …

Interdiffusion behavior between Cr and Zr and its effect on the microcracking behavior in the Cr-coated Zr-4 alloy

JS Jiang, DQ Wang, MY Du, XF Ma, CX Wang… - Nuclear Science and …, 2021‏ - Springer
Abstract High-temperature chromium (Cr)-zirconium (Zr) interdiffusion commonly occurs in
Cr-coated zircaloys applied for enhanced accident-tolerant fuel (ATF) claddings. Such …

Mechanical behavior of a chromium coating on a zirconium alloy substrate at room temperature

DV Nguyen, M Le Saux, L Gélébart, JC Brachet… - Journal of Nuclear …, 2022‏ - Elsevier
The mechanical behavior of a 15 µm-thick chromium coating deposited on a zirconium alloy
substrate using a particular physical vapor deposition process is studied at room …

In situ X-ray computed micro-tomography imaging of failure processes in Cr-coated Zircaloy nuclear fuel cladding materials

G Yuan, JP Forna-Kreutzer, J Ell, H Barnard, BR Maier… - Materials & Design, 2023‏ - Elsevier
Abstract Chromium (Cr)-coated Zircaloy fuel cladding has been considered a promising
candidate materials system for accident tolerant fuels. In this work, two types of Cr coatings …

Temperature-time dependence and mechanisms of redox reaction in Cr-coated Zr alloy cladding during steam oxidation at 900–1250℃

J Deng, JD Zuo, D Geng, Q Sun, Z Song… - Journal of Nuclear …, 2024‏ - Elsevier
The structural integrity of the Cr coating can be significantly affected with increasing
temperature during steam oxidation. Herein, the elemental diffusion, layered structure, and …

Unveiling fracture mechanics of a curved coating/substrate system by combined digital image correlation and numerical finite element analyses

DE Burden, TM Harrell, CH Bumgardner… - Engineering Fracture …, 2024‏ - Elsevier
A mechanism of coated, curved substrate failure is characterized via a C-ring compression
test and multiscale modeling analysis. Coating crack formation is driven by sudden through …

Quantifying the effect of tow architecture variability on the performance of biaxially braided composite tubes

FM Heim, JT Daspit, X Li - Composites Part B: Engineering, 2020‏ - Elsevier
Targeted experiments are performed with stereoscopic digital image correlation to quantify
the effect of irregular braid structure on the local surface mechanical response of carbon …

Unveiling damage mechanisms of chromium-coated zirconium-based fuel claddings at LWR operating temperature by in-situ digital image correlation

DC Roache, CH Bumgardner, TM Harrell… - Surface and Coatings …, 2022‏ - Elsevier
Here, we investigate the coupled thermomechanical fracture mechanisms of coated nuclear
fuel claddings at Light Water Reactor (LWR) operating temperatures. These coated …