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

Works (16)

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, 120, 103184.

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

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, 3, 1–20.

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

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

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