Review of manufacturing technologies for coated accident tolerant fuel cladding
This article reviewed the near-term development status of accident tolerant fuel (ATF)
cladding to increase the safety of nuclear power generation. The key to near-term …
cladding to increase the safety of nuclear power generation. The key to near-term …
Multilayer (TiN, TiAlN) ceramic coatings for nuclear fuel cladding
In an attempt to develop an accident-tolerant fuel (ATF) that can delay the deleterious
consequences of loss-of-coolant-accidents (LOCA), multilayer coatings were deposited onto …
consequences of loss-of-coolant-accidents (LOCA), multilayer coatings were deposited onto …
Superior corrosion resistance properties of TiN-based coatings on Zircaloy tubes in supercritical water
Thin films of TiN and Ti 0.35 Al 0.65 N nanocomposite were deposited on polished Zircaloy-
4 tubes. After exposure to supercritical water for 48 h, the coated tubes are remarkably intact …
4 tubes. After exposure to supercritical water for 48 h, the coated tubes are remarkably intact …
Synthesis of plasma-nitrided Cr coatings on HT9 steel for advanced chemical barrier property in a nuclear cladding application
Chromium–chromium nitride multi-coating barriers were synthesized on HT9 steel disks
using the electroplating and radiofrequency (RF) plasma nitriding techniques, respectively …
using the electroplating and radiofrequency (RF) plasma nitriding techniques, respectively …
High-intensity low energy titanium ion implantation into zirconium alloy
AI Ryabchikov, EB Kashkarov, NS Pushilina… - Applied Surface …, 2018 - Elsevier
This research describes the possibility of ultra-high dose deep titanium ion implantation for
surface modification of zirconium alloy Zr-1Nb. The developed method based on repetitively …
surface modification of zirconium alloy Zr-1Nb. The developed method based on repetitively …
[HTML][HTML] Mechanical analysis of surface-coated zircaloy cladding
A structural model for stress distributions of coated Zircaloy subjected to realistic incore
pressure difference, thermal expansion, irradiation-induced axial growth, and creep has …
pressure difference, thermal expansion, irradiation-induced axial growth, and creep has …
Size-dependent radiation tolerance in ion irradiated TiN/AlN nanolayer films
Interface effects on ion-irradiation tolerance properties are investigated in nanolayered
TiN/AlN films with individual layer thickness varied from 5 nm to 50 nm, prepared by pulsed …
TiN/AlN films with individual layer thickness varied from 5 nm to 50 nm, prepared by pulsed …
Unveiling damage mechanisms of chromium-coated zirconium-based fuel claddings by coupling digital image correlation and acoustic emission
DC Roache, A Jarama, CH Bumgardner… - Materials Science and …, 2020 - Elsevier
Coated nuclear fuel claddings offer a promising, near-term solution to address the demand
for next-generation, accident-tolerant fuel systems. It is expected that they will possess …
for next-generation, accident-tolerant fuel systems. It is expected that they will possess …
Evaluation of the interfacial shear strength and residual stress of TiAlN coating on ZIRLO™ fuel cladding using a modified shear-lag model approach
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 …
coating on Zr–Nb–Sn–Fe alloy (ZIRLO™) substrate designed to improve corrosion …
The characterization of electrodeposited chromium barriers for nuclear reactor cladding application
S Yeo, JH Kim, SH Eom - Journal of Nuclear Materials, 2020 - Elsevier
A layer of Cr coating on the inner surface of HT9 cladding is a promising barrier to hinder
fuel and cladding chemical interaction (FCCI) in sodum-coolded fast reactors (SFRs). Cr …
fuel and cladding chemical interaction (FCCI) in sodum-coolded fast reactors (SFRs). Cr …