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

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 (18)

2021 journal article

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

Journal of Nuclear Engineering.

By: M. Avramova, A. Abarca, J. Hou & K. Ivanov

Source: ORCID
Added: March 8, 2021

2021 journal article

Propagating neutronic uncertainties for FFTF LOFWOS Test #13

NUCLEAR ENGINEERING AND DESIGN, 375, 111047.

By: A. Rivas, N. Stauff, T. Sumner & J. Hou

Sources: ORCID, Web Of Science
Added: March 23, 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, M. Avramova & K. Ivanov

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. Stauff, J. Hou & T. Kim

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, J. Hou, G. Grasso, K. Ivanov & F. Franceschini

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. Wang, L. Cao, Z. Liu & J. Hou

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, S. Bhaskar, D. Ziyad, P. Balestra, C. Fiorina, J. Hou, N. Smith, M. Avramova

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, 5, 1–20.

By: S. Sihlangu, V. Naicker, J. Hou & F. Reitsma

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), 1618–1637.

By: K. Zeng, J. Hou, K. Ivanov & M. Jessee

Source: ORCID
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, 1–9.

By: Q. Li, Y. Jiao, M. Avramova, P. Chen, J. Yu, J. Chen, J. Hou

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), 1591–1598.

By: L. Wang, J. Guo, F. Li, J. Hou & 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, 177–189.

By: J. Hou, K. Ivanov, V. Boyarinov & P. Fomichenko

Sources: NC State University Libraries, ORCID
Added: August 6, 2018

2016 journal article

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

Progress in Nuclear Energy, 88, 58–74.

By: J. Hou, S. Qvist, R. Kellogg & E. Greenspan

Sources: NC State University Libraries, 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, 93–114.

By: S. Qvist, J. Hou & E. Greenspan

Sources: NC State University Libraries, 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, 335–342.

By: J. Hou, H. Choi & K. Ivanov

Sources: NC State University Libraries, ORCID
Added: August 6, 2018

2014 journal article

Assessment of MICROX-2 Code With New ENDF/B-VII Release 0 Master Libraries

Nucl Technol, 6(3), 305–316 .

By: J. Hou, H. Choi & K. Ivanov

Sources: NC State University Libraries, ORCID
Added: August 6, 2018

2014 journal article

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

Annals of Nuclear Energy, 64, 256–263.

By: J. Hou, H. Choi & K. Ivanov

Sources: NC State University Libraries, 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.

By: D. Osborne, J. Hou, G. Graves & L. Miller

Source: ORCID
Added: May 24, 2019

Employment

2019 - present

North Carolina 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

2010 - 2013

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

2008 - 2011

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

2001 - 2005

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