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Jia Hou, Ph.D. - Publications

Affiliations: 
2013 Pennsylvania State University, State College, PA, United States 
Area:
Nuclear Engineering, General Engineering
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9 high-probability publications. We are testing a new system for linking publications to authors. You can help! If you notice any inaccuracies, please sign in and mark papers as correct or incorrect matches. If you identify any major omissions or other inaccuracies in the publication list, please let us know.

Year Citation  Score
2020 Hou J, Avramova M, Ivanov K. Best-Estimate Plus Uncertainty Framework for Multiscale, Multiphysics Light Water Reactor Core Analysis Science and Technology of Nuclear Installations. 2020: 1-18. DOI: 10.1155/2020/7526864  0.568
2020 Trivedi I, Hou J, Grasso G, Ivanov K, Franceschini F. Nuclear Data Uncertainty Quantification and Propagation for Safety Analysis of Lead-Cooled Fast Reactors Science and Technology of Nuclear Installations. 2020: 1-14. DOI: 10.1155/2020/3961095  0.37
2020 Zeng K, Stauff NE, Hou J, Kim TK. Development of multi-objective core optimization framework and application to sodium-cooled fast test reactors Progress in Nuclear Energy. 120: 103184. DOI: 10.1016/J.Pnucene.2019.103184  0.358
2020 Altahhan MR, Bhaskar S, Ziyad D, Balestra P, Fiorina C, Hou J, Smith N, Avramova M. Preliminary design and analysis of Liquid Fuel Molten Salt Reactor using multi-physics code GeN-Foam Nuclear Engineering and Design. 369: 110826. DOI: 10.1016/J.Nucengdes.2020.110826  0.58
2020 Wan C, Sui Z, Wang B, Cao L, Liu Z, Hou J. Nuclear-data uncertainty propagation in transient simulation for the C5G7-TD benchmark problem Annals of Nuclear Energy. 140: 107122. DOI: 10.1016/J.Anucene.2019.107122  0.361
2019 Zeng K, Hou J, Ivanov K, Jessee MA. Uncertainty Quantification and Propagation of Multiphysics Simulation of the Pressurized Water Reactor Core Nuclear Technology. 205: 1618-1637. DOI: 10.1080/00295450.2019.1580533  0.327
2018 Li Q, Jiao Y, Avramova M, Chen P, Yu J, Chen J, Hou J. Development, verification and application of a new model for active nucleation site density in boiling systems Nuclear Engineering and Design. 328: 1-9. DOI: 10.1016/J.Nucengdes.2017.12.027  0.554
2015 Hou J, Choi H, Ivanov KN. Development of an iterative diffusion-transport method based on MICROX-2 cross section libraries Annals of Nuclear Energy. 77: 335-342. DOI: 10.1016/J.Anucene.2014.11.014  0.317
2014 Hou J, Choi H, Ivanov KN. Self-shielding models of MICROX-2 code: Review and updates Annals of Nuclear Energy. 64: 256-263. DOI: 10.1016/J.Anucene.2013.10.005  0.366
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