Jason Hou

A System Predictive Maintenance Framework for Advanced Reactors Using a Data-Driven Digital Twin

Rivas, A., Delipei, G. K., & Hou, J. (2024, August 3). NUCLEAR SCIENCE AND ENGINEERING, Vol. 8.

A component diagnostic and prognostic framework for pump bearings based on deep learning with data augmentation

RELIABILITY ENGINEERING & SYSTEM SAFETY, 247.

A system diagnostic and prognostic framework based on deep learning for advanced reactors

PROGRESS IN NUCLEAR ENERGY, 170.

Development and evaluation of parallel simulated annealing algorithm for reactor core optimization problems

Nuclear Science and Technology Open Research.

Modeling a generic Pebble Bed High-Temperature Gas-Cooled Reactor to perform load-following using Simulink

NUCLEAR ENGINEERING AND DESIGN, 428.

Prototyping of a Machine Learning-Based Burnup Measurement Capability for Pebble Bed Reactor Fuel

Rollins, N., Allan, I., & Hou, J. (2024, April 4). NUCLEAR SCIENCE AND ENGINEERING, Vol. 4.

Reinforcement Learning-Based Control Sequence Optimization for Advanced Reactors

JOURNAL OF NUCLEAR ENGINEERING, 5(3), 209–225.

Source term analysis of FeCrAl accident tolerant fuel using MELCOR

ANNALS OF NUCLEAR ENERGY, 202.

An Efficient High-to-Low Iterative Method for Light Water Reactor Analysis Based on NEAMS Tools

Nuclear Science and Engineering, 197(8), 1700–1716.

A Novel Method for Controlling Crud Deposition in Nuclear Reactors Using Optimization Algorithms and Deep Neural Network Based Surrogate Models

Eng.

A hybrid neutronics method with novel fission diffusion synthetic acceleration for criticality calculations

NUCLEAR ENGINEERING AND TECHNOLOGY, 55(4), 1428–1438.

CTF-PARCS Core Multi-Physics Computational Framework for Efficient LWR Steady-State, Depletion and Transient Uncertainty Quantification

ENERGIES, 15(14).

Nuclear data uncertainty propagation applied to the versatile test reactor conceptual design

NUCLEAR ENGINEERING AND DESIGN, 392.

Predictions of component Remaining Useful Lifetime Using Bayesian Neural Network

PROGRESS IN NUCLEAR ENERGY, 146.

Innovations in Multi-Physics Methods Development, Validation, and Uncertainty Quantification

Journal of Nuclear Engineering.

Methodology for Discontinuity Factors Generation for Simplified P-3 Solver Based on Nodal Expansion Formulation

ENERGIES, 14(20).

Propagating neutronic uncertainties for FFTF LOFWOS Test #13

NUCLEAR ENGINEERING AND DESIGN, 375.

Summary of comparative analysis and conclusions from OECD/NEA LWR-UAM benchmark Phase I

NUCLEAR ENGINEERING AND DESIGN, 384.

Best-Estimate Plus Uncertainty Framework for Multiscale, Multiphysics Light Water Reactor Core Analysis

Science and Technology of Nuclear Installations.

Nuclear Data Uncertainty Quantification and Propagation for Safety Analysis of Lead-Cooled Fast Reactors

Science and Technology of Nuclear Installations.

Preliminary design and analysis of Liquid Fuel Molten Salt Reactor using multi-physics code GeN-Foam

Nuclear Engineering and Design, 369, 110826.

Development of multi-objective core optimization framework and application to sodium-cooled fast test reactors

Progress in Nuclear Energy.

Further development of methodology to model TRISO fuel and BISO absorber particles and related uncertainty quantification using SCALE 6

Journal of Nuclear Science and Technology, 56(8), 690–709.

Nuclear-data uncertainty propagation in transient simulation for the C5G7-TD benchmark problem

Annals of Nuclear Energy, 140, 107122.

Uncertainty Quantification and Propagation of Multiphysics Simulation of the Pressurized Water Reactor Core

Nuclear Technology, 205(12), 1618–1637.

Development, verification and application of a new model for active nucleation site density in boiling systems

Nuclear Engineering and Design, 328, 1–9.

Effect of Nuclear Data on Fuel Element Neutronic Characteristics of Pebble-bed High Temperature Gas-cooled Reactor

Atomic Energy Science and Technology, 51(9), 1591–1598.

OECD/NEA benchmark for time-dependent neutron transport calculations without spatial homogenization

NUCLEAR ENGINEERING AND DESIGN, 317, 177–189.

3D in-core fuel management optimization for breed-and-burn reactors

PROGRESS IN NUCLEAR ENERGY, 88, 58–74.

Design and performance of 2D and 3D-shuffled breed-and-burn cores

ANNALS OF NUCLEAR ENERGY, 85, 93–114.

ASSESSMENT OF MICROX-2 CODE WITH NEW ENDF/B-VII RELEASE 0 MASTER LIBRARIES

NUCLEAR TECHNOLOGY, 186(3), 305–316.

Development of an iterative diffusion-transport method based on MICROX-2 cross section libraries

ANNALS OF NUCLEAR ENERGY, 77, 335–342.

Self-shielding models of MICROX-2 code: Review and updates

ANNALS OF NUCLEAR ENERGY, 64, 256–263.

Development of a Modern Pressurized Water Reactor Simulator: Instrumentation, Design and Data Acquisition

2007 IEEE Nuclear Science Symposium Conference Record.