Publications

Sep, 2026

ORNL Report

2026 Description of the P-LOTS Post-Processor for NGSAM Scenario Comparative Cost Analysis

Aug, 2026

ORNL Report

Arcturus Project FY 2025 Q2

Mar, 2026

Conference Paper

Effect of Decay Time on Criticality Safety Analyses for High Burnup and Extended Enrichment Fuels

Mar, 2026

Conference Paper

ASSESSMENT OF VALIDATION FOR BURNUP CREDIT CALCULATIONS FOR LEU+ AND HIGH BURNUP FUEL

Mar, 2026

Conference Paper

Nuclide Importance to Shielding Calculations in Advanced Reactor Spent Fuel Transportation and Storage

Mar, 2026

Conference Paper

Review of Available Critical Experiments and Critical Experiments Facilities to Perform High-Assay Low-Enriched Uranium Fuel Transport Validation for Advanced Reactor Deployment

Mar, 2026

Conference Paper

Burnup Credit Loading Curves for High-Burnup and Extended Enrichment Fuels

Mar, 2026

Conference Paper

Current Overview of Neutron Moderator Thermal Scattering Kernels for HALEU-Fueled Advanced Reactors

Sep, 2025

ORNL Report

Arcturus Project FY 2025 Q3

Jul, 2025

Journal

Impact of recent ENDF nuclear data update, high initial enrichment and high burnup fuel on critical experiments applicability determination via the integral index ck for burnup credit validation

In 2012, NUREG/CR-7109 reported on the validation of burnup credit calculations involving major and minor actinides and major fission products which was investigated for pressurized and boiling water reactor (PWR and BWR) fuel enrichments up to 5 wt% 235U and assembly-average burnups up to 60 GWd/MTU. Recently, there has been interest in increasing the maximum enrichment u…

May, 2025

ORNL Report

Validation Studies for High Burnup and Extended Enrichment Fuels in Burnup Credit Criticality Safety Analyses

Feb, 2025

Conference Paper

Bias and Bias Uncertainty for High Burnup and Extended Enrichment Fuels in Criticality Safety Analyses Validation Studies