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Paridhi Athe
Paridhi Athe
Ph.D., Nuclear Engineering, North Carolina State University
在 ncsu.edu 的电子邮件经过验证
标题
引用次数
引用次数
年份
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
942009
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
612021
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
292022
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
202013
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
162021
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
122019
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
72020
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
62012
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
42021
A Framework for Predictive Capability Maturity Assessment of Computer Simulation Codes.
P Athe
42018
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
42017
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
32014
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
22020
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
22018
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
22017
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
12021
Investigation of similarity metrics for simulation based scaling analysis
P Athe, N Dinh, H Abdel-Khalik
Advances in Thermal Hydraulics 2016 (ATH 2016), 2016
12016
Are modeling uncertainties properly considered in neutronics data assimilation analysis?
P Athe, HS Abdel-Khalik
12015
Mutual Information: A Generalization of Similarity Indices
P Athe, H Abdel-Khalik
Trans. Am. Nucl. Soc. 111, 751, 2014
12014
Testing Generative Pre-trained Transformer for Knowledge Abstraction and Reasoning for Nuclear Reactor Design and Safety Applications
P Athe, N Dinh
2023
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