Thermophysical and Mechanical Analyses of UO2-36.4vol % BeO Fuel Pellets with Zircaloy, SiC, and FeCrAl Claddings

Multiphysics coupled modeling of light water reactor fuel performance

(2016) Rong Liu et al.   PROGRESS IN NUCLEAR ENERGY

Neutronics and fuel performance evaluation of accident tolerant FeCrAl cladding under normal operation conditions

(2015) Xu Wu et al.   ANNALS OF NUCLEAR ENERGY

Fabrication and measurement of hoop strength of SiC triplex tube for nuclear fuel cladding applications

(2015) Daejong Kim et al.   JOURNAL OF NUCLEAR MATERIALS

Adhesion property and high-temperature oxidation behavior of Cr-coated Zircaloy-4 cladding tube prepared by 3D laser coating

(2015) Hyun-Gil Kim et al.   JOURNAL OF NUCLEAR MATERIALS

Fully coupled multiphysics modeling of enhanced thermal conductivity UO 2 –BeO fuel performance in a light water reactor

(2015) R. Liu et al.   NUCLEAR ENGINEERING AND DESIGN

Accident tolerant fuels for LWRs: A perspective

(2013) S.J. Zinkle et al.   JOURNAL OF NUCLEAR MATERIALS

Advanced oxidation-resistant iron-based alloys for LWR fuel cladding

(2013) K.A. Terrani et al.   JOURNAL OF NUCLEAR MATERIALS

Enhanced thermal conductivity of uranium dioxide–silicon carbide composite fuel pellets prepared by Spark Plasma Sintering (SPS)

(2012) S. Yeo et al.   JOURNAL OF NUCLEAR MATERIALS

Modeling and Measurement of Thermal Properties of Ceramic Composite Fuel for Light Water Reactors

(2008) Ryan Latta et al.   HEAT TRANSFER ENGINEERING