Center for Nuclear Energy Facilities and Structures

Digital engineering workflow for effective management of ITAAC using text analytics and 4D BIM concept for construction of nuclear power plants

Nuclear Engineering and Design.

Automated digital transformation for pedestrian suspension bridges using hybrid semantic structure from motion

Automation in Construction.

Uncertainty Quantification Framework for High-Temperature Gas-Cooled Reactors Using VSOP and DAKOTA

Delipei, G. K., Altahhan, M., Rouxelin, P., Sen, S., George, N., Avramova, M., & Ivanov, K. (2025, May 15). NUCLEAR SCIENCE AND ENGINEERING, Vol. 5.

Development of Serpent/CTF External Coupling for the OECD/NEA TVA-WB1 Benchmark Activities

Albagami, T., Rouxelin, P., Abarca, A., Palmtag, S., Avramova, M., & Ivanov, K. (2025, April 27). NUCLEAR SCIENCE AND ENGINEERING, Vol. 4.

Sensitivity and uncertainty analysis in pebble-bed reactors: A study using the High-Temperature Code Package (HCP)

ANNALS OF NUCLEAR ENERGY, 219.

A scaffolding model for designing and implementing work-integrated learning experiences based on the analysis of the university and company's arrangements

Diaz, B., Delgado, C., Han, K., & Lynch, C. (2025, April 2). HIGHER EDUCATION, Vol. 4.

A vision-based weigh-in-motion approach for vehicle load tracking and identification

Lam, P. T., Lee, J., Lee, Y., Nguyen, X. T., Vy, V., Han, K., & Yoon, H. (2025, March 16). COMPUTER-AIDED CIVIL AND INFRASTRUCTURE ENGINEERING.

High-Resolution flow boiling simulations with multiple nucleation sites in mini-channels with offset strip fins

APPLIED THERMAL ENGINEERING, 268.

Analysis of two pedagogical approaches to foster discipline integrations in an educational data mining class using communities of practice

INTERNATIONAL JOURNAL OF STEM EDUCATION, 12(1).

Autonomous Navigation and Positioning of a Real-Time and Automated Mobile Robotic Welding System

JOURNAL OF CONSTRUCTION ENGINEERING AND MANAGEMENT, 151(5).

NEAMS IRP challenge problem 3: Mixing in large enclosures and thermal stratification

NUCLEAR ENGINEERING AND DESIGN, 433.

Development and application of two-step uncertainty propagation and sensitivity analysis methodology for fast reactor safety analysis

NUCLEAR ENGINEERING AND DESIGN, 433.

Building a multiscale framework: An overview of the NEAMS thermal-hydraulics integrated research project

NUCLEAR ENGINEERING AND DESIGN, 433.

Data-driven prediction and uncertainty quantification of PWR crud-induced power shift using convolutional neural networks

ENERGY, 316.

An Integrated Framework for Uncertainty Quantification in High Temperature Gas Cooled Reactors using the HCP Time-Dependent Multiphysics Code and DAKOTA Toolkit

BEPU-2024 Best Estimate Plus Uncertainty International Conference. Presented at the BEPU-2024 Best Estimate Plus Uncertainty International Conference, Lucca, Italy.

An Integrated Multi-Physics Modeling and Uncertainty Quantification Framework for High Temperature Gas-Cooled Reactors using VSOP and DAKOTA

BEPU-2024 Best Estimate Plus Uncertainty International Conference. Presented at the BEPU-2024 Best Estimate Plus Uncertainty International Conference, Lucca, Italy.

Doppler Effective Temperature Database Based on Monte Carlo Simulations

BEPU-2024 Best Estimate Plus Uncertainty International Conference. Presented at the BEPU-2024 Best Estimate Plus Uncertainty International Conference, Lucca, Italy.

Elucidating the Uncertainties Introduced by Data-Driven Machine Learning Models

BEPU-2024 Best Estimate Plus Uncertainty International Conference. Presented at the BEPU-2024 Best Estimate Plus Uncertainty International Conference, Lucca, Italy.

Multi-Physics Uncertainty Analysis Study using Single-Physics Modeling to Support Verification and Validation

BEPU-2024 Best Estimate Plus Uncertainty International Conference. Presented at the BEPU-2024 Best Estimate Plus Uncertainty International Conference, Lucca, Italy.

Shape Optimization Under Uncertainty (Shape-OUU) through a DAKOTA/MOOSE Framework

BEPU-2024 Best Estimate Plus Uncertainty International Conference. Presented at the BEPU-2024 Best Estimate Plus Uncertainty International Conference, Lucca, Italy.

Development of Serpent -- CTF External Coupling for the OECD/NEA TVA WB1 Benchmark Activities

Editorial: 26th International Conference on Structural Mechanics in Reactor Technology

Sadegh-Azar, H., & Gupta, A. (2025, February). NUCLEAR ENGINEERING AND DESIGN, Vol. 432.

Investigation of Transients with Serpent using the OECD/NEA C5G7-TD Benchmark

JOINT INTERNATIONAL CONFERENCE ON SUPERCOMPUTING IN NUCLEAR APPLICATIONS + MONTE CARLO, SNA + MC 2024, Vol. 302.

Behavior of External Socket Connections for the Seismic Design of Bridges

18th World Conference on Earthquake Engineering (WCEE). Presented at the 18th World Conference on Earthquake Engineering (WCEE), Milan, Italy.

Crack Kinematics in Large-Scale Shear Critical Reinforced Concrete Deep Beam Experiments: Towards Improved Aggregate Interlock Constitutive Models

SMiRT-27. Presented at the SMiRT-27, Yokohama, Division I, Japan.