Nuclear Engineering

Comparison of excitation and kinetic temperatures in a laser-produced plasma using absorption spectroscopy

OPTICS LETTERS, 48(7), 1942–1945.

Data-Driven High-to-Low for Coarse Grid System Thermal Hydraulics

Iskhakov, A. S., Leite, V. C., Merzari, E., & Dinh, N. T. (2023, April 28). NUCLEAR SCIENCE AND ENGINEERING, Vol. 4.

Solving the Neutron Transport Equation for Microreactor Modeling Using Unstructured Meshes and Exascale Computing Architectures

Dawn, W. C., & Palmtag, S. (2023, May 11). NUCLEAR SCIENCE AND ENGINEERING, Vol. 5.

FLASSH 1.0: Thermal Scattering Law Evaluation and Cross-Section Generation for Reactor Physics Applications

Fleming, N. C., Manring, C. A., Laramee, B. K., Crozier, J. P. W., Lee, E., & Hawari, A. I. (2023, April 21). NUCLEAR SCIENCE AND ENGINEERING.

Investigating the applicability of human reliability analysis methods during early design stages of non-light-water nuclear power plants

Progress in Nuclear Energy.

Re duce d order models for thermal radiative transfer problems based on moment equations and data-driven approximations of the Eddington tensor

JOURNAL OF QUANTITATIVE SPECTROSCOPY & RADIATIVE TRANSFER, 296.

Effect of focus ring with external circuit on cathode edge sheath dynamics in a capacitively coupled plasma

Journal of Vacuum Science & Technology A.

Verification methods for drift–diffusion reaction models for plasma simulations

Plasma Sources Science and Technology.

Fuel performance uncertainty quantification and sensitivity analysis in the presence of epistemic and aleatoric sources of uncertainties

FRONTIERS IN ENERGY RESEARCH, 11.

Temperature-Dependent Morphological Evolution during Corrosion of the Ni-20Cr Alloy in Molten Salt Revealed by Multiscale Imaging

ACS APPLIED MATERIALS & INTERFACES, 15(10), 13772–13782.

Gel growth and characterization of Cs3Bi2Br9 perovskite single crystals for radiation detection

Frontiers in Physics, 11.

A combined strategy for dynamic probabilistic risk assessment of fission battery designs using EMRALD and DEPM

PROGRESS IN NUCLEAR ENERGY, 160.

Shielding and corrosion properties of the Alloy 709 as canister material for spent nuclear fuel dry casks

DEFENCE TECHNOLOGY, 21, 116–124.

Preservation of kinetics parameters generated by Monte Carlo calculations in two-step deterministic calculations

EPJ NUCLEAR SCIENCES & TECHNOLOGIES, 9.

Benchmark of Neutron Thermalization in Graphite Using a Pulsed Slowing-Down-Time Experiment

Lee, E., Fleming, N. C., & Hawari, A. I. (2023, February 26). NUCLEAR SCIENCE AND ENGINEERING.

Prediction and uncertainty quantification of SAFARI-1 axial neutron flux profiles with neural networks

ANNALS OF NUCLEAR ENERGY, 188.

Intragranular irradiation-assisted stress corrosion cracking (IASCC) of 316L stainless steel made by laser direct energy deposition additive manufacturing: Delta ferrite-dislocation channel interaction

JOURNAL OF NUCLEAR MATERIALS, 577.

Inference of main ion particle transport coefficients with experimentally constrained neutral ionization during edge localized mode recovery on DIII-D

NUCLEAR FUSION, 63(4).

Direct numerical simulation of heat transfer on a deformable vapor bubble rising in superheated liquid

PHYSICS OF FLUIDS, 35(2).

Data-Driven RANS Turbulence Closures for Forced Convection Flow in Reactor Downcomer Geometry

Iskhakov, A. S., Tai, C.-K., Bolotnov, I. A., Nguyen, T., Merzari, E., Shaver, D. R., & Dinh, N. T. (2023, March 16). NUCLEAR TECHNOLOGY, Vol. 3.