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

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

UPDATED U3SI2 THERMAL CREEP MODEL AND SENSITIVITY ANALYSIS OF THE U3SI2-SIC ADVANCED TECHNOLOGY FUEL

(2020) J.A Yingling 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

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

Transient Reactor Test (TREAT) Facility Design and Experiment Capability

(2019) Chad L. Pope 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

Development of Advanced Instrumentation for Transient Testing

(2019) Colby Jensen et al.   NUCLEAR TECHNOLOGY

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

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

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

Narrowing transient testing pulse widths to enhance LWR RIA experiment design in the TREAT facility

(2018) John D. Bess et al.   ANNALS OF NUCLEAR ENERGY

Multispectral pyrometry for surface temperature measurement of oxidized Zircaloy claddings

(2017) B. Bouvry et al.   INFRARED PHYSICS & TECHNOLOGY

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

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

Continuous SiC fiber, CVI SiC matrix composites for nuclear applications: Properties and irradiation effects

(2013) Yutai Katoh et al.   JOURNAL OF NUCLEAR MATERIALS

Multidimensional multiphysics simulation of nuclear fuel behavior

(2012) R.L. Williamson et al.   JOURNAL OF NUCLEAR MATERIALS

Thermodynamic study of the U–Si system

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