Mixed analytical model to estimate the anisotropic effective thermal conductivity and in-reactor performance of metallic microcell UO2

Thermal conductivity prediction of UO2-BeO composite fuels and related decisive features discovery via convolutional neural network

(2022) Zhanpeng Gong et al.   ACTA MATERIALIA

Performance analysis of nuclear reactor core loaded with Accident-Tolerant Fuel: Mo/Cr metallic microcell UO2 pellets and CrAl coating

(2022) Eun Jeong et al.   ANNALS OF NUCLEAR ENERGY

Prospects for additive manufacturing of nuclear fuel forms

(2022) Andrew T. Nelson   PROGRESS IN NUCLEAR ENERGY

Analysis of pellet-to-cladding gap closure for a metallic micro-cell pellet under normal operating conditions

(2021) Yang-Hyun Koo et al.   JOURNAL OF NUCLEAR MATERIALS

Evaluation of thermophysical properties of UO2-10 Vol% Mo nuclear fuel pellets

(2021) Murali Krishna Tummalapalli et al.   JOURNAL OF NUCLEAR MATERIALS

Enhancing thermal conductivity of UO2 with the addition of UB2 via conventional sintering techniques

(2021) Jennifer K. Watkins et al.   JOURNAL OF NUCLEAR MATERIALS

UO2 + 5 vol% ZrB2 nano composite nuclear fuels with full boron retention and enhanced oxidation resistance

(2020) Tiankai Yao et al.   CERAMICS INTERNATIONAL

U3Si2 and UO2 composites densified by spark plasma sintering for accident-tolerant fuels

(2020) Bowen Gong et al.   JOURNAL OF NUCLEAR MATERIALS

Optimization of thermal conductivity of UO2–Mo composite with continuous Mo channel based on finite element method and machine learning

(2020) Biaojie Yan et al.   INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER

Impact of uranium oxide (UO2) fuel with molybdenum (Mo) inserts on pressurized water reactor performance and safety

(2020) Jacob P. Gorton et al.   JOURNAL OF NUCLEAR MATERIALS

Fabrication and thermophysical properties of UO2-UB2 and UO2-UB4 composites sintered via spark plasma sintering

(2020) E. Kardoulaki et al.   JOURNAL OF NUCLEAR MATERIALS

Fabrication of UO2-Mo composite fuel with enhanced thermal conductivity from sol-gel feedstock

(2019) S.C. Finkeldei et al.   JOURNAL OF NUCLEAR MATERIALS

Uranium dioxide - Molybdenum composite fuel pellets with enhanced thermal conductivity manufactured via spark plasma sintering

(2019) J. Buckley et al.   JOURNAL OF NUCLEAR MATERIALS

Fission gas release in the micro-cell fuel pellet under normal operating conditions: A simplified approach based on UO2 pellet experience

(2019) Yang-Hyun Koo et al.   JOURNAL OF NUCLEAR MATERIALS

Conductive inserts to reduce nuclear fuel temperature

(2019) Pavel G. Medvedev et al.   JOURNAL OF NUCLEAR MATERIALS

Enhanced thermal conductivity accident tolerant fuels for improved reactor safety – A comprehensive review

(2018) Wei Zhou et al.   ANNALS OF NUCLEAR ENERGY

Development status of microcell UO 2 pellet for accident-tolerant fuel

(2018) Dong-Joo Kim et al.   Nuclear Engineering and Technology

Irradiation testing of enhanced uranium oxide fuels

(2018) Klara Insulander Björk et al.   ANNALS OF NUCLEAR ENERGY

Numerical characterization of micro-cell UO 2 Mo pellet for enhanced thermal performance

(2016) Heung Soo Lee et al.   JOURNAL OF NUCLEAR MATERIALS

Synthesis and preservation of graphene-supported uranium dioxide nanocrystals

(2016) Hanyu Ma et al.   JOURNAL OF NUCLEAR MATERIALS

Development Status of Accident-tolerant Fuel for Light Water Reactors in Korea

(2016) Hyun-Gil Kim et al.   Nuclear Engineering and Technology

Fabrication methods and thermal hydraulics analysis of enhanced thermal conductivity UO2–BeO fuel in light water reactors

(2015) Wenzhong Zhou et al.   ANNALS OF NUCLEAR ENERGY

Synthesis and sintering of UN-UO 2 fuel composites

(2015) Brian J. Jaques et al.   JOURNAL OF NUCLEAR MATERIALS

UO 2 –UN composites with enhanced uranium density and thermal conductivity

(2015) Jae Ho Yang et al.   JOURNAL OF NUCLEAR MATERIALS

The behaviour under irradiation of molybdenum matrix for inert matrix fuel containing americium oxide (CerMet concept)

(2015) E. D'Agata et al.   JOURNAL OF NUCLEAR MATERIALS

Fabrication of micro-cell UO 2 –Mo pellet with enhanced thermal conductivity

(2015) Dong-Joo Kim et al.   JOURNAL OF NUCLEAR MATERIALS

Spark plasma sintering of diamond-reinforced uranium dioxide composite fuel pellets

(2015) Zhichao Chen et al.   NUCLEAR ENGINEERING AND DESIGN

Influence of Carbon Nanotube Dispersion in UO2–Carbon Nanotube Ceramic Matrix Composites Utilizing Spark Plasma Sintering

(2015) Andrew Cartas et al.   NUCLEAR TECHNOLOGY

The influence of SiC particle size and volume fraction on the thermal conductivity of spark plasma sintered UO2–SiC composites

(2013) Sunghwan Yeo 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 thermal conductivity in UO2 with BeO additions as a function of microstructure

(2009) D.S. Li 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