Effects of ion irradiation on Cr, CrN, and TiAlCrN coated Zircaloy-4 for accident tolerant fuel claddings

Cr-coated Zr-4 alloy prepared by electroplating and its in situ He+ irradiation behavior

(2020) Minjiang Huang et al.   JOURNAL OF NUCLEAR MATERIALS

Study of the oxidation behavior of CrN coating on Zr alloy in air

(2019) Chuiyi Meng et al.   JOURNAL OF NUCLEAR MATERIALS

Point defect sink strength of low-angle tilt grain boundaries: a phase field dislocation climb model

(2019) Pengchuang Liu et al.   INTERNATIONAL JOURNAL OF PLASTICITY

Radiation response of Ti2AlC MAX phase coated Zircaloy-4 for accident tolerant fuel cladding

(2019) Jonathan G. Gigax et al.   JOURNAL OF NUCLEAR MATERIALS

Effect of gas pressure and bias potential on oxidation resistance of Cr coatings

(2019) Xiujie He et al.   ANNALS OF NUCLEAR ENERGY

Effects of ion irradiation on chromium coatings of various thicknesses on a zirconium alloy

(2019) Li Jiang et al.   JOURNAL OF NUCLEAR MATERIALS

Loop and void damage during heavy ion irradiation on nanocrystalline and coarse grained tungsten: Microstructure, effect of dpa rate, temperature, and grain size

(2018) O. El-Atwani et al.   ACTA MATERIALIA

Examining the influence of grain size on radiation tolerance in the nanocrystalline regime

(2018) Christopher M. Barr et al.   APPLIED PHYSICS LETTERS

Microstructural evolution of nanochannel CrN films under ion irradiation at elevated temperature and post-irradiation annealing

(2018) Jun Tang et al.   JOURNAL OF NUCLEAR MATERIALS

In situ study on enhanced heavy ion irradiation tolerance of porous Mg

(2018) Jin Li et al.   SCRIPTA MATERIALIA

Irradiation resistance of vacuum arc chromium coatings for zirconium alloy fuel claddings

(2018) A.S. Kuprin et al.   JOURNAL OF NUCLEAR MATERIALS

Evaluation of corrosion and oxidation behaviors of TiAlCrN coatings for nuclear fuel cladding

(2018) Xian-Feng Ma et al.   SURFACE & COATINGS TECHNOLOGY

The effect of irradiation temperature on damage structures in proton-irradiated zirconium alloys

(2018) M. Topping et al.   JOURNAL OF NUCLEAR MATERIALS

Effect of ion and neutron irradiation on oxide of PHWR fuel tube material

(2018) Gargi Choudhuri et al.   JOURNAL OF NUCLEAR MATERIALS

Microstructure evolution of recrystallized Zircaloy-4 under charged particles irradiation

(2017) M. Gaumé et al.   JOURNAL OF NUCLEAR MATERIALS

Effect of heavy ion irradiation on thermodynamically equilibrium Zr-Excel alloy

(2017) Hongbing Yu et al.   JOURNAL OF NUCLEAR MATERIALS

Dislocation loop formation by swift heavy ion irradiation of metals

(2017) Galvin S Khara et al.   JOURNAL OF PHYSICS-CONDENSED MATTER

Neutronic evaluation of coating and cladding materials for accident tolerant fuels

(2016) Ian Younker et al.   PROGRESS IN NUCLEAR ENERGY

The relationship between grain boundary structure, defect mobility and grain boundary sink efficiency

(2015) Blas Pedro Uberuaga et al.   Scientific Reports

Orientation mapping of nanostructured materials using transmission Kikuchi diffraction in the scanning electron microscope

(2012) Patrick W. Trimby   ULTRAMICROSCOPY

Atomistic study of grain boundary sink strength under prolonged electron irradiation

(2011) Yongfeng Zhang et al.   JOURNAL OF NUCLEAR MATERIALS

SRIM – The stopping and range of ions in matter (2010)

(2010) James F. Ziegler et al.   NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS