Publications

Sep, 2026

Conference Paper

Estimation of Void Fraction History Using Post-irradiation Fuel Isotopics

Jul, 2026

Journal

The 0E2 benchmarks for PWR UO2 decay heat: an analysis from the NEA WPNCS

This paper presents the work performed in the subgroup 16 of the Working Party for Nuclear Criticality Safety (WPNCS) of the OECD Nuclear Energy Agency. The main goal was to define two decay heat benchmarks for Spent Nuclear Fuel (one pincell and one assembly), perform calculations and compare and analyze the results in light of existing calorimetric measurements. The sele…

Jul, 2026

Conference Paper

Nuclear Data Impact on Key Metrics for a Representative Molten Chloride Fast Reactor Model

Nuclear data are an essential component of the foundation on which all modeling and simulation methods and tools are relying upon, from the front end to the back end of the nuclear fuel cycle. In this study, the impact of uncertainties in nuclear data is investigated for a representative molten chloride fast reactor, for several important metrics, including eigenvalue, rea…

Jul, 2026

Conference Paper

Impact of Nuclear Data on Fuel Inventory for HALEU-Fueled Sodium-Cooled Fast Reactors

Jul, 2026

Conference Paper

On the Statistical Uncertainty of Monte Carlo-Calculated Scattering Sensitivities

Sensitivity coefficients calculated with Monte Carlo codes are widely used for nuclear data uncertainty quantification in the modeling and simulation of complex 3D reactor systems. This study systematically compares sensitivity coefficients and associated statistical uncertainties for the multiplication factor and fuel temperature reactivity across multiple Monte Carlo cod…

Apr, 2026

Journal

Nuclear Data Impact Assessment for the HTR-10 Pebble-Bed Reactor Using SCALE

The HTR-10 was used as a representative pebble-bed high-temperature gas-cooled reactor in this assessment of nuclear data’s impact on important reactor and spent fuel metrics, including safety-related quantities such as the effective multiplication factor (keff), temperature reactivity feedback, spent fuel inventory, and decay heat. Using the SCALE code system tools and EN…

Mar, 2026

Conference Paper

Nuclide Inventory Validation: Effect of Nuclear Data Libraries

Mar, 2026

Conference Paper

Assessing criticality implications of porosity misrepresentation in ENDF/B-VIII.1 graphite TSLs and small angle neutron scattering in nuclear graphite

Mar, 2026

Conference Paper

Nuclide Importance to Decay Heat in Advanced Reactors’ Spent Fuel Transportation and Storage

Mar, 2026

Conference Paper

EDIM Local Power History and Burnup Inference Based on Destructive Assay Data

Mar, 2026

Conference Paper

Nuclear Data Impact on HTR-10 Pebble Bed Reactor Metrics

Mar, 2026

Conference Paper

Estimation of Void Fraction History Using Post-irradiation Fuel Isotopics