Publications

Aug, 2026

Journal

Irradiation of UC1+x kernels using the MiniFuel vehicle: Microstructure, phase analysis, and initial post-irradiation examination

Uranium carbide is a candidate fuel form for a wide range of advanced reactors, including larger Generation IV reactors as well as small modular reactors and microreactors. However, its commercial deployment timeline faces challenges via traditional qualification approaches. To address this issue, an accelerated fission rate irradiation test was performed to collect basic…

Mar, 2026

Conference Paper

BISON VALIDATION TO PRESSUREIZED WATER REACTOR HIGH-BURNUP POST-IRRADIATION EXAMINATION DATA

Jan, 2026

ORNL Report

Statistical Assessment of Buffer Response and IPyC Cracking to Support Expanded TRISO Operation Envelope

Sep, 2025

ORNL Report

Analysis of Fission Product Release from Furnace-Tested TRISO Particles

High temperature testing of intact TRISO particles previously irradiated in AGR-1 experiments was performed. Higher levels of Ag release were found at 1300 C compared to both lower and higher temperatures. Additionally, some of the particles released a majority of their inventory while others did not appear to release radioactivity under similar irradiation and testing co…

Aug, 2025

ORNL Report

Finite Element Analysis Framework Applicable to Different SiC Cladding Concepts: 3D Image-Based Modeling

Mar, 2025

ORNL Report

ORNL Interim Progress Report #4 CRADA NFE-21-08656: Development of Advanced Fuel Materials for the BWXT Advanced Nuclear Reactor

Feb, 2025

Journal

MicroMechanical Response of SiC-OPyC Layer in TRISO Fuel Particles

Tristructural isotropic (TRISO)–coated particle fuel is a proposed fuel for multiple advanced reactor concepts. The performance of the particle depends on whether the silicon carbide (SiC) layer remains intact to prevent the release of metallic and gaseous fission products. Mechanical fracture of the SiC layer is a potential failure mode under various fuel configurations a…

Dec, 2024

Journal

Ordered Particle Packing in Dense TRISO/SiC Fuel Elements and Preliminary Assessment of Neutronic and Thermomechanical Characteristics

Detailed analysis of the particle distribution in Transformational Challenge Reactor fuel elements indicates that particle packing is not random; instead, it follows a relatively ordered structure near fuel element surfaces. Discrete particle neutronic simulations indicate that the core reactivity is not impacted when assuming homogenization of particles with the silicon c…

Oct, 2024

ORNL Report

BISON Validation to Commercially Irradiated Fuel Post Irradiation Examination Data

Oct, 2024

ORNL Report

ORNL Interim Progress Report #3 CRADA NFE-21-08656: Development of Advanced Fuel Materials for the BWXT Advanced Nuclear Reactor

Jul, 2024

ORNL Report

NEAMS Burnup Extension Accomplishments and Remaining Modeling Gaps

Mar, 2024

ORNL Report

ORNL Interim Progress Report #2 CRADA NFE-21-08656: Development of Advanced Fuel Materials for the BWXT Advanced Nuclear Reactor