Post-transient examination of performance of uranium silicide fuel and silicon-carbide composite cladding under reactivity-initiated accident conditions

Transient testing of uranium silicide fuel in zircaloy and silicon carbide cladding

(2021) David Kamerman et al.   ANNALS OF NUCLEAR ENERGY

Spark plasma sintering (SPS) densified U3Si2 pellets: Microstructure control and enhanced mechanical and oxidation properties

(2020) Bowen Gong et al.   JOURNAL OF ALLOYS AND COMPOUNDS

Non-Destructive Post-irradiation Examination Results of the First Modern Fueled Experiments in TREAT

(2020) Jason Schulthess et al.   JOURNAL OF NUCLEAR MATERIALS

Performance of U3Si2 in an LWR following a cladding breach during normal operation

(2020) R.T. Sweet et al.   JOURNAL OF NUCLEAR MATERIALS

Aluminum-doped U3Si2 composite fuels with enhanced oxidation resistance

(2020) Afiqa Mohamad et al.   JOURNAL OF ALLOYS AND COMPOUNDS

3Y-TZP Toughened and Oxidation-resistant U3Si2 Composites for Accident Tolerant Fuels

(2020) Afiqa Mohamad et al.   JOURNAL OF NUCLEAR MATERIALS

Hydrothermal Corrosion of First-Generation Dual-Purpose Coatings on Silicon Carbide for Accident-Tolerant Fuel Cladding

(2020) Peter J. Doyle et al.   JOURNAL OF NUCLEAR MATERIALS

Mechanical behavior of SiC/SiC composites after exposure in high temperature liquid sodium for Sodium Fast Reactors applications

(2020) J. Braun et al.   JOURNAL OF NUCLEAR MATERIALS

Postirradiation examinations of low burnup U3Si2 fuel for light water reactor applications

(2019) Fabiola Cappia et al.   JOURNAL OF NUCLEAR MATERIALS

Development of Irradiation Test Devices for Transient Testing

(2019) Nicolas Woolstenhulme et al.   NUCLEAR TECHNOLOGY

C-ring testing of nuclear grade silicon carbide composites at temperatures up to 1900 °C

(2019) Kirill Shapovalov et al.   JOURNAL OF NUCLEAR MATERIALS

U3Si2-SiC fuel performance analysis in BISON during normal operation

(2019) Wei Li et al.   ANNALS OF NUCLEAR ENERGY

Core-to-specimen energy coupling results of the first modern fueled experiments in TREAT

(2019) Nicolas Woolstenhulme et al.   ANNALS OF NUCLEAR ENERGY

Fuel performance optimization of U3Si2-SiC design during normal, power ramp and RIA conditions

(2019) Yanan He et al.   NUCLEAR ENGINEERING AND DESIGN

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

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

U 3 Si 2 behavior in H 2 O environments: Part II, pressurized water with controlled redox chemistry

(2018) A.T. Nelson et al.   JOURNAL OF NUCLEAR MATERIALS

Accident tolerant fuel cladding development: Promise, status, and challenges

(2018) Kurt A. Terrani   JOURNAL OF NUCLEAR MATERIALS

Grain size and phase purity characterization of U3Si2 fuel pellets

(2018) Rita E. Hoggan et al.   JOURNAL OF NUCLEAR MATERIALS

Failure behavior of SiC/SiC composite tubes under strain rates similar to the pellet-cladding mechanical interaction phase of reactivity-initiated accidents

(2018) M. Nedim Cinbiz et al.   JOURNAL OF NUCLEAR MATERIALS

Investigation of elevated-temperature mechanical properties of δ-hydride precipitate in Zircaloy-4 fuel cladding tubes using nanoindentation

(2017) Siddharth Suman et al.   JOURNAL OF ALLOYS AND COMPOUNDS

Experimental design and analysis for irradiation of SiC/SiC composite tubes under a prototypic high heat flux

(2017) Christian M. Petrie et al.   JOURNAL OF NUCLEAR MATERIALS

Microstructure studies of interdiffusion behavior of U 3 Si 2 /Zircaloy-4 at 800 and 1000 °C

(2017) Lingfeng He et al.   JOURNAL OF NUCLEAR MATERIALS

Determination of mechanical behavior of U 3 Si 2 nuclear fuel by microindentation method

(2017) Kathryn E. Metzger et al.   PROGRESS IN NUCLEAR ENERGY

Reactor Safety Gap Evaluation of Accident-Tolerant Components and Severe Accident Analysis

(2016) M. T. Farmer et al.   NUCLEAR SCIENCE AND ENGINEERING

Uranium silicide pellet fabrication by powder metallurgy for accident tolerant fuel evaluation and irradiation

(2015) Jason M. Harp et al.   JOURNAL OF NUCLEAR MATERIALS

Characterization of SiC–SiC composites for accident tolerant fuel cladding

(2015) C.P. Deck et al.   JOURNAL OF NUCLEAR MATERIALS

Stress analysis and probabilistic assessment of multi-layer SiC-based accident tolerant nuclear fuel cladding

(2015) J.G. Stone et al.   JOURNAL OF NUCLEAR MATERIALS

Thermophysical properties of U3Si2 to 1773 K

(2015) J.T. White et al.   JOURNAL OF NUCLEAR MATERIALS

The effect of fuel thermal conductivity on the behavior of LWR cores during loss-of-coolant accidents

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

Evaluation of neutron economical effect of new cladding materials in light water reactors

(2013) Akito Oizumi et al.   JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY

A review on the clad failure studies

(2011) Tanweer Alam et al.   NUCLEAR ENGINEERING AND DESIGN

Fabrication of SiC–SiC composites for fuel cladding in advanced reactor designs

(2011) C.P. Deck et al.   PROGRESS IN NUCLEAR ENERGY

Atomistic simulations of void migration under thermal gradient in UO2

(2009) Tapan G. Desai et al.   ACTA MATERIALIA

Thermodynamic study of the U–Si system

(2009) A. Berche et al.   JOURNAL OF NUCLEAR MATERIALS