Jason Hou

Also known as: Jia Hou; Jiayu Hou

https://orcid.org/0000-0002-1144-1632

Nuclear energy, Reactor modeling and simulation, Advanced reactors, Machine learning, Uncertainty

Jason Hou is an advocate of nuclear energy and the mission of his research is to promote nuclear energy by investigating advanced reactor designs and developing improved reactor modeling and simulation methods.

Works (26)

Updated: July 28th, 2023 05:08

2023 journal article

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

NUCLEAR ENGINEERING AND TECHNOLOGY, 55(4), 1428โ€“1438.

By: J. Chenโ€‰ n, J. Hou nโ€‰ & K. Ivanov nโ€‰

co-author countries: United States of America ๐Ÿ‡บ๐Ÿ‡ธ
author keywords: Monte Carlo; Hybrid neutronics method; Diffusion synthetic acceleration
Sources: ORCID, Web Of Science
Added: December 23, 2022

2023 journal article

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

Nuclear Science and Engineering, 197(8), 1700โ€“1716.

By: K. Ni nโ€‰ & J. Hou nโ€‰

co-author countries: United States of America ๐Ÿ‡บ๐Ÿ‡ธ
author keywords: Lattice calculation; cross-section generation; iterative method; acceleration
Sources: ORCID, Web Of Science, Crossref
Added: February 21, 2023

2022 journal article

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

Eng.

co-author countries: United States of America ๐Ÿ‡บ๐Ÿ‡ธ
Source: ORCID
Added: November 25, 2022

2022 journal article

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

ENERGIES, 15(14).

co-author countries: United States of America ๐Ÿ‡บ๐Ÿ‡ธ
author keywords: multi-physics; CTF; PARCS; LWR; uncertainty quantification
Sources: ORCID, Web Of Science
Added: July 20, 2022

2022 journal article

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

NUCLEAR ENGINEERING AND DESIGN, 392.

By: A. Rivas n, N. Martinโ€‰*, S. Bays*, G. Palmiotti*, Z. Xuโ€‰* & J. Hou nโ€‰

co-author countries: United States of America ๐Ÿ‡บ๐Ÿ‡ธ
author keywords: Uncertainty Propagation; Neutronics; Versatile Test Reactor; Nuclear Data Uncertainty; Sodium-Cooled Fast Reactor; Sensitivity Analysis
Sources: ORCID, Web Of Science
Added: April 20, 2022

2022 journal article

Predictions of component Remaining Useful Lifetime Using Bayesian Neural Network

PROGRESS IN NUCLEAR ENERGY, 146.

By: A. Rivas n, G. Delipeiโ€‰ n & J. Hou nโ€‰

co-author countries: United States of America ๐Ÿ‡บ๐Ÿ‡ธ
author keywords: Prognostics and Health Management; Remaining Useful Life; Bayesian Neural Network; Deep learning; Predictive maintenance; C-MAPSS dataset
Sources: ORCID, Web Of Science
Added: March 1, 2022

2021 journal article

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

Journal of Nuclear Engineering.

co-author countries: United States of America ๐Ÿ‡บ๐Ÿ‡ธ
Source: ORCID
Added: March 8, 2021

2021 journal article

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

ENERGIES, 14(20).

By: Y. Xu n, J. Hou nโ€‰ & K. Ivanov nโ€‰

co-author countries: United States of America ๐Ÿ‡บ๐Ÿ‡ธ
author keywords: transport-corrected SP3; nodal expansion method; generalized equivalence theory; discontinuity factors
Sources: ORCID, Web Of Science
Added: October 11, 2021

2021 journal article

Propagating neutronic uncertainties for FFTF LOFWOS Test #13

NUCLEAR ENGINEERING AND DESIGN, 375.

By: A. Rivas n, N. Stauffโ€‰*, T. Sumner* & J. Hou nโ€‰

co-author countries: United States of America ๐Ÿ‡บ๐Ÿ‡ธ
author keywords: Uncertainty propagation; Neutronics; Thermal hydraulics; Nuclear data uncertainty; Sodium-cooled fast reactor; Sensitivity analysis; Loss of flow without scram
Sources: ORCID, Web Of Science
Added: March 23, 2021

2021 journal article

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

NUCLEAR ENGINEERING AND DESIGN, 384.

By: G. Delipeiโ€‰ n, J. Hou nโ€‰, M. Avramova n, P. Rouxelin n & K. Ivanov nโ€‰

co-author countries: United States of America ๐Ÿ‡บ๐Ÿ‡ธ
author keywords: LWR; Uncertainty analysis; Benchmark; Neutronics; Summary
Sources: ORCID, Web Of Science
Added: October 1, 2021

2020 journal article

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

Science and Technology of Nuclear Installations.

By: J. Hou nโ€‰, M. Avramovaโ€‰ n & K. Ivanovโ€‰ n

co-author countries: United States of America ๐Ÿ‡บ๐Ÿ‡ธ
Source: ORCID
Added: August 1, 2020

2020 journal article

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

Progress in Nuclear Energy.

By: K. Zeng n, N. Stauffโ€‰*, J. Hou nโ€‰ & T. Kim*

co-author countries: United States of America ๐Ÿ‡บ๐Ÿ‡ธ
Source: ORCID
Added: November 14, 2019

2020 journal article

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

Science and Technology of Nuclear Installations.

By: I. Trivedi n, J. Hou nโ€‰, G. Grassoโ€‰*, K. Ivanovโ€‰ n & F. Franceschini*

co-author countries: Italy ๐Ÿ‡ฎ๐Ÿ‡น United States of America ๐Ÿ‡บ๐Ÿ‡ธ
Source: ORCID
Added: August 13, 2020

2020 journal article

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

Annals of Nuclear Energy, 140, 107122.

By: C. Wan*, Z. Sui*, B. Wangโ€‰*, L. Caoโ€‰*, Z. Liu* & J. Hou nโ€‰

co-author countries: China ๐Ÿ‡จ๐Ÿ‡ณ United States of America ๐Ÿ‡บ๐Ÿ‡ธ
author keywords: Uncertainty analysis; Nuclear-data uncertainties; C5G7 benchmark problem; Transient simulation
Source: ORCID
Added: October 24, 2019

2020 journal article

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

Nuclear Engineering and Design, 369, 110826.

By: M. Ramzy Altahhan n, S. Bhaskar n, D. Ziyad n, P. Balestraโ€‰ n, C. Fiorinaโ€‰*, J. Hou nโ€‰, N. Smith*, M. Avramovaโ€‰ n

co-author countries: Switzerland ๐Ÿ‡จ๐Ÿ‡ญ United States of America ๐Ÿ‡บ๐Ÿ‡ธ
author keywords: Molten Salt Reactor; CFD; Multiphysics; GeN-Foam; OpenFOAM; Nuclear energy; Liquid fuel
Source: ORCID
Added: November 30, 2020

2019 journal article

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), 690โ€“709.

By: S. Sihlanguโ€‰*, V. Naicker*, J. Hou nโ€‰ & F. Reitsmaโ€‰*

co-author countries: Austria ๐Ÿ‡ฆ๐Ÿ‡น United States of America ๐Ÿ‡บ๐Ÿ‡ธ South Africa ๐Ÿ‡ฟ๐Ÿ‡ฆ
author keywords: Double-heterogeneity; DOUBLEHET; coated fuel particle; HTGR; uncertainty; SCALE 6; burnable poison; criticality analysis; packing; randomization
Source: ORCID
Added: May 24, 2019

2019 journal article

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

Nuclear Technology, 205(12), 1618โ€“1637.

By: K. Zeng n, J. Hou nโ€‰, K. Ivanov nโ€‰ & M. Jesseeโ€‰*

co-author countries: United States of America ๐Ÿ‡บ๐Ÿ‡ธ
author keywords: Uncertainty quantification; stochastic sampling; PWR; rod ejection accident; multiphysics simulation
Sources: ORCID, Crossref
Added: May 24, 2019

2018 journal article

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

Nuclear Engineering and Design, 328, 1โ€“9.

co-author countries: China ๐Ÿ‡จ๐Ÿ‡ณ United States of America ๐Ÿ‡บ๐Ÿ‡ธ
Source: ORCID
Added: May 24, 2019

2017 journal article

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

Atomic Energy Science and Technology, 51(9), 1591โ€“1598.

By: L. Wang, J. Guo, F. Li, J. Houโ€‰ & K. Ivanov

Source: NC State University Libraries
Added: November 21, 2020

2017 journal article

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

NUCLEAR ENGINEERING AND DESIGN, 317, 177โ€“189.

By: J. Hou nโ€‰, K. Ivanov nโ€‰, V. Boyarinov* & P. Fomichenko*

co-author countries: Russian Federation ๐Ÿ‡ท๐Ÿ‡บ United States of America ๐Ÿ‡บ๐Ÿ‡ธ
author keywords: Neutron transients; Space-time benchmark C5G7-TD; Kinetics parameters
Sources: Web Of Science, ORCID
Added: August 6, 2018

2016 journal article

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

PROGRESS IN NUCLEAR ENERGY, 88, 58โ€“74.

By: J. Hou*โ€‰, S. Qvistโ€‰*, R. Kellogg* & E. Greenspan*

co-author countries: Sweden ๐Ÿ‡ธ๐Ÿ‡ช United States of America ๐Ÿ‡บ๐Ÿ‡ธ
author keywords: Breed-and-burn reactor; Peak radiation damage; 3D fuel shuffling optimization; Simulated annealing; Optimal core design
Sources: Web Of Science, ORCID
Added: August 6, 2018

2015 journal article

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

ANNALS OF NUCLEAR ENERGY, 85, 93โ€“114.

By: S. Qvistโ€‰*, J. Hou*โ€‰ & E. Greenspan*

co-author countries: Sweden ๐Ÿ‡ธ๐Ÿ‡ช United States of America ๐Ÿ‡บ๐Ÿ‡ธ
author keywords: Breed and burn; Traveling Wave; Core design; Fast reactor; Shuffling; LMFBR
Sources: Web Of Science, ORCID
Added: August 6, 2018

2015 journal article

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

ANNALS OF NUCLEAR ENERGY, 77, 335โ€“342.

By: J. Hou*โ€‰, H. Choiโ€‰* & K. Ivanov*โ€‰

co-author countries: United States of America ๐Ÿ‡บ๐Ÿ‡ธ
author keywords: 2-D lattice calculation; Iterative Diffusion-Transport method; Cross section generation; Boundary condition
Sources: Web Of Science, ORCID
Added: August 6, 2018

2014 journal article

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

NUCLEAR TECHNOLOGY, 186(3), 305โ€“316.

co-author countries: United States of America ๐Ÿ‡บ๐Ÿ‡ธ
author keywords: MICROX-2; cross-section library; ENDF/B-VII
Sources: Web Of Science, ORCID
Added: August 6, 2018

2014 journal article

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

ANNALS OF NUCLEAR ENERGY, 64, 256โ€“263.

By: J. Hou*โ€‰, H. Choiโ€‰* & K. Ivanov*โ€‰

co-author countries: United States of America ๐Ÿ‡บ๐Ÿ‡ธ
author keywords: MICROX-2; Resonance self-shielding; Dancoff factor
Sources: Web Of Science, ORCID
Added: August 6, 2018

2007 conference paper

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

2007 IEEE Nuclear Science Symposium Conference Record.

co-author countries: United States of America ๐Ÿ‡บ๐Ÿ‡ธ
Source: ORCID
Added: May 24, 2019

Employment

Updated: July 24th, 2022 22:54

2022 - present

North Carolina State University Raleigh, North Carolina, US
Associate Professor Nuclear Engineering

2019 - 2022

NC State University Raleigh, NC, US
Assistant Professor Nuclear Engineering

2016 - 2019

North Carolina State University Raleigh, NC, US
Research Assistant Professor Nuclear Engineering

2014 - 2015

University of California Berkeley Berkeley, CA, US
Postdoctoral Scholar Nuclear Engineering

Education

Updated: November 29th, 2023 10:50

2010 - 2013

Pennsylvania State University University Park University Park, PA, US
Ph.D. Nuclear Engineering

2008 - 2010

University of Michigan College of Engineering Ann Arbor, MI, US
M.S. Nuclear Engineering and Radiological Sciences

2006 - 2007

University of Tennessee at Knoxville Knoxville, Tennessee, US
M.S. Nuclear Engineering

2001 - 2005

Tsinghua University Beijing, Beijing, CN
B.S. Engineering Physics

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