Publications

Sep, 2026

Journal

Mesh-based multiphysics coupling acceleration for fusion neutronics through clustering for fusion blanket applications

Accurate modeling of particle transport within fusion blankets is essential for predicting performance metrics such as heat deposition and the tritium breeding ratio (TBR). However, high-fidelity coupling of thermal fluids from computational fluid dynamics (CFD) to neutronics simulations often incurs significant computational costs due to the complexity of surface intersec…

Sep, 2026

ORNL Report

Fuel Cycle Transition Studies to 4X Nuclear Capacity Expansion

Jul, 2026

Journal

First Wall Design of a Tokamak Pilot Plant Using a Monte Carlo Model for 3-D Heat Flux Deposition

We present a method for calculating the heat fluxes deposited on nonaxisymmetric tokamak first wall components, allowing for a first-of-its-kind model for power handling in the tokamak far scrape-off layer (SOL). The DIV3D Monte Carlo model features strict global power conservation and can calculate the finite cross-field plasma transport into magnetically-shadowed regions…

Jun, 2026

ORNL Report

Dynamic Cost Modeling and Analysis

May, 2026

Journal

Impact of high-fidelity temperature feedback modeling on fusion blanket neutronics

Accurate modeling and simulation of neutron and gamma transport and interactions within fusion tokamaks represents a critical area of research for fusion energy development. This paper presents a method to couple computational fluid dynamics (CFD) results to high-fidelity neutronics analyses, to explore the fusion neutronics’ feedback to blanket temperature and density. Th…

Apr, 2026

ORNL Report

Fuel Cycle Cost Analysis by Integrating Fuel Cycle Scenario and Economic Tools and Data

Apr, 2026

Conference Paper

Enhanced Neutronics Analysis of HFIR LEU Optimized Fuel Design via Improved PHAME Framework

Apr, 2026

Journal

Investigation of irradiation damage and heat deposition: a comparative analysis for HEU-to-LEU conversion in HFIR

The planned conversion of the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory from highly enriched uranium (HEU) to low-enriched uranium (LEU) fuel requires detailed evaluation of experiment-relevant parameters to ensure continued performance for materials testing and isotope production. This study presents the first comprehensive assessment of displaceme…

Mar, 2026

Conference Paper

SCALE 6.3 Enhancements to the Polaris Lattice Physics Code for Light-Water Reactor Confirmatory Analysis

Mar, 2026

Conference Paper

Heat Deposition Analysis of Target Materials in the High Flux Isotope Reactor for HEU and LEU Cores

Mar, 2026

Conference Paper

Sensitivity and Validation Studies of Plutonium-238 Production with Shift and ORIGEN

Mar, 2026

Conference Paper

Comparative Analysis of Heat Deposition Rates and DPA in the HFIR Flux Trap to Support LEU Conversion