A Comparative Study of 6T, 8T and 9T Decanano SRAM cell P Athe, S Dasgupta 2009 IEEE Symposium on Industrial Electronics & Applications 2, 889-894, 2009 | 94 | 2009 |
Development and assessment of a nearly autonomous management and control system for advanced reactors L Lin, P Athe, P Rouxelin, M Avramova, A Gupta, R Youngblood, J Lane, ... Annals of Nuclear Energy 150, 107861, 2021 | 61 | 2021 |
Digital-twin-based improvements to diagnosis, prognosis, strategy assessment, and discrepancy checking in a nearly autonomous management and control system L Lin, P Athe, P Rouxelin, M Avramova, A Gupta, R Youngblood, J Lane, ... Annals of Nuclear Energy 166, 108715, 2022 | 29 | 2022 |
Characterization of multiphase flow in bubble columns using KT-1 signature and fractal dimension P Athe, S Shakya, P Munshi, A Luke, D Mewes Flow Measurement and Instrumentation 33, 122-137, 2013 | 20 | 2013 |
Development of the machine learning-based safety significant factor inference model for diagnosis in autonomous control system J Lee, L Lin, P Athe, N Dinh Annals of Nuclear Energy 162, 108443, 2021 | 16 | 2021 |
A framework for assessment of predictive capability maturity and its application in nuclear thermal hydraulics P Athe, N Dinh Nuclear Engineering and Design 354, 110201, 2019 | 12 | 2019 |
Development and assessment of data-driven digital twins in a nearly autonomous management and control system for advanced reactors L Lin, P Rouxelin, P Athe, N Dinh, J Lane International conference on nuclear engineering 83761, V001T06A027, 2020 | 7 | 2020 |
Analysis of phase fraction distribution in multi-phase bubble columns using KT-1 signature and Fractal dimension P Athe, S Shakya, P Munshi, A Luke, D Mewes Proceedings of 6th International Symposium on Process Tomography, Cape Town …, 2012 | 6 | 2012 |
Assessment of the Predictive Capability of VERA—CS for CASL Challenge Problems P Athe, C Jones, N Dinh Journal of Verification, Validation and Uncertainty Quantification 6 (2), 021003, 2021 | 4 | 2021 |
A Framework for Predictive Capability Maturity Assessment of Computer Simulation Codes. P Athe | 4 | 2018 |
Initial Verification and Validation Assessment for VERA C Jones, A Hetzler, N Dinh, P Athe, M Sieger Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2017 | 4 | 2017 |
Determination of bias, bias uncertainty, and coverage using data assimilation P Athe, H Abdel-Khalik, U Mertyurek Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2014 | 3 | 2014 |
Development and assessment of a nearly autonomous management and control system during a single loss of flow accident L Lin, P Athe, P Rouxelin, N Dinh, J Lane International Conference on Nuclear Engineering 83761, V001T06A033, 2020 | 2 | 2020 |
Updated Verification and Validation Assessment for VERA C Jones, A Hetzler, N Dinh, P Athe, M Sieger Sandia National Lab.(SNL-NM), Albuquerque, NM (United States), 2018 | 2 | 2018 |
A framework to support assessment of predictive capability maturity of multiphysics simulation codes P Athe, N Dinh Consortium of Advanced Simulation of Light Water Reactor, U.S. Department of …, 2017 | 2 | 2017 |
Trusting Machine Learning in Nuclear Plant Control: A Reasoning-Based Discrepancy Checker B Hanna, L Lin, P Athe, T Son, N Dinh 12th Nuclear Plant Instrumentation, Control and Human-Machine Interface …, 2021 | 1 | 2021 |
Investigation of similarity metrics for simulation based scaling analysis P Athe, N Dinh, H Abdel-Khalik Advances in Thermal Hydraulics 2016 (ATH 2016), 2016 | 1 | 2016 |
Are modeling uncertainties properly considered in neutronics data assimilation analysis? P Athe, HS Abdel-Khalik | 1 | 2015 |
Mutual Information: A Generalization of Similarity Indices P Athe, H Abdel-Khalik Trans. Am. Nucl. Soc. 111, 751, 2014 | 1 | 2014 |
Testing Generative Pre-trained Transformer for Knowledge Abstraction and Reasoning for Nuclear Reactor Design and Safety Applications P Athe, N Dinh | | 2023 |