Jia Hou, Ph.D.
Affiliations: | 2013 | Pennsylvania State University, State College, PA, United States |
Area:
Nuclear Engineering, General EngineeringGoogle:
"Jia Hou"Parents
Sign in to add mentor| Kostadin Ivanov | grad student | 2013 | Penn State | |
| (The development and application of an improved reactor analysis model for fast reactors.) | ||||
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Publications
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| Hou J, Avramova M, Ivanov K. (2020) Best-Estimate Plus Uncertainty Framework for Multiscale, Multiphysics Light Water Reactor Core Analysis Science and Technology of Nuclear Installations. 2020: 1-18 |
| Trivedi I, Hou J, Grasso G, et al. (2020) Nuclear Data Uncertainty Quantification and Propagation for Safety Analysis of Lead-Cooled Fast Reactors Science and Technology of Nuclear Installations. 2020: 1-14 |
| Zeng K, Stauff NE, Hou J, et al. (2020) Development of multi-objective core optimization framework and application to sodium-cooled fast test reactors Progress in Nuclear Energy. 120: 103184 |
| Altahhan MR, Bhaskar S, Ziyad D, et al. (2020) Preliminary design and analysis of Liquid Fuel Molten Salt Reactor using multi-physics code GeN-Foam Nuclear Engineering and Design. 369: 110826 |
| Wan C, Sui Z, Wang B, et al. (2020) Nuclear-data uncertainty propagation in transient simulation for the C5G7-TD benchmark problem Annals of Nuclear Energy. 140: 107122 |
| Zeng K, Hou J, Ivanov K, et al. (2019) Uncertainty Quantification and Propagation of Multiphysics Simulation of the Pressurized Water Reactor Core Nuclear Technology. 205: 1618-1637 |
| Li Q, Jiao Y, Avramova M, et al. (2018) Development, verification and application of a new model for active nucleation site density in boiling systems Nuclear Engineering and Design. 328: 1-9 |
| Hou J, Choi H, Ivanov KN. (2015) Development of an iterative diffusion-transport method based on MICROX-2 cross section libraries Annals of Nuclear Energy. 77: 335-342 |
| Hou J, Choi H, Ivanov KN. (2014) Self-shielding models of MICROX-2 code: Review and updates Annals of Nuclear Energy. 64: 256-263 |