Paridhi Athe

Knowledge Representation to Support EMDAP Implementation in Advanced Reactor Licensing Applications. (2023). 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20). Retrieved from https://www.ans.org/meetings/nureth20/session/view-1883/

Athe, P., Athe, P., Srivastava, S., Athe, P., & Shukla, S. K. (2022, June 23). Design of Multiple Resonant Reflectance Filter Using One-Dimensional Fibonacci Superconductor Photonic Crystal. JOURNAL OF SUPERCONDUCTIVITY AND NOVEL MAGNETISM, Vol. 35. https://doi.org/10.1007/s10948-022-06318-1

Lin, L., Athe, P., Rouxelin, P., Avramova, M., Gupta, A., Youngblood, R., … Dinh, N. (2022). Digital-twin-based improvements to diagnosis, prognosis, strategy assessment, and discrepancy checking in a nearly autonomous management and control system. ANNALS OF NUCLEAR ENERGY, 166. https://doi.org/10.1016/j.anucene.2021.108715

Athe, P., Jones, C., & Dinh, N. (2021). Assessment of the Predictive Capability of VERA-CS for CASL Challenge Problems. Journal of Verification, Validation and Uncertainty Quantification, 6(2). https://doi.org/10.1115/1.4050248

Lin, L., Athe, P., Rouxelin, P., Avramova, M., Gupta, A., Youngblood, R., … Dinh, N. (2021). Development and assessment of a nearly autonomous management and control system for advanced reactors. Annals of Nuclear Energy, 150. https://doi.org/10.1016/j.anucene.2020.107861

Lee, J., Lin, L., Athe, P., & Dinh, N. (2021). Development of the Machine Learning-based Safety Significant Factor Inference Model for Diagnosis in Autonomous Control System. ANNALS OF NUCLEAR ENERGY, 162. https://doi.org/10.1016/j.anucene.2021.108443

Application of Predictive Capability Maturity Model for Assessment of VERA-CS for CASL Challenge Problems. (2020). The Consortium for Advanced Simulation of Light Water Reactors Virtual Meeting, 2020 ANS Virtual Winter Meeting. Retrieved from https://www.ans.org/pubs/proceedings/article-49246/

Lin, L., Athe, P., Rouxelin, P., Dinh, N., & Lane, J. (2020). Development and assessment of a nearly autonomous management and control system during a single loss of flow accident. International Conference on Nuclear Engineering, Proceedings, ICONE, 1. https://doi.org/10.1115/ICONE2020-16908

Lin, L., Rouxelin, P., Athe, P., Dinh, N., & Lane, J. (2020). Development and assessment of data-driven digital twins in a nearly autonomous management and control system for advanced reactors. International Conference on Nuclear Engineering, Proceedings, ICONE, 1. https://doi.org/10.1115/ICONE2020-16813

Athe, P., & Dinh, N. (2019). A framework for assessment of predictive capability maturity and its application in nuclear thermal hydraulics. NUCLEAR ENGINEERING AND DESIGN, 354. https://doi.org/10.1016/j.nucengdes.2019.110201

Athe, P., Dinh, N., & Abdel-Khalik, H. (2016). Investigation of similarity metrics for simulation based scaling analysis. International Topical Meeting on Advances in Thermal Hydraulics 2016, ATH 2016, 409–425. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-84992126794&partnerID=MN8TOARS

Athe, P., & Abdel-Khalik, H. S. (2014). Are modeling uncertainties properly considered in neutronics data assimilation analysis? Proceedings of the International Conference on Physics of Reactors, PHYSOR 2014. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-85014738422&partnerID=MN8TOARS

Athe, P., Mertyurek, U., & Abdel-Khalik, H. S. (2014). Determination of bias, bias uncertainty, and coverage using data assimilation. Transactions of the American Nuclear Society, 111, 1299–1302. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-84939206281&partnerID=MN8TOARS

Athe, P., & Abdel-Khalik, H. (2014). Mutual information: A generalization of similarity indices. Transactions of the American Nuclear Society, 111, 751–754. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-84939167247&partnerID=MN8TOARS

Athe, P., Shakya, S., Munshi, P., Luke, A., & Mewes, D. (2013). Characterization of multiphase flow in bubble columns using KT-1 signature and fractal dimension. FLOW MEASUREMENT AND INSTRUMENTATION, 33, 122–137. https://doi.org/10.1016/j.flowmeasinst.2013.05.005

Analysis of multiphase flow in bubble column reactor using KT-1 signature and fractal dimension. (2012). 6th International symposium on Process Tomography.

Athe, P., & Dasgupta, S. (2009). A comparative study of 6T, 8T and 9T decanano SRAM cell. 2009 IEEE Symposium on Industrial Electronics and Applications, ISIEA 2009 - Proceedings, 2, 889–894. https://doi.org/10.1109/ISIEA.2009.5356318

Trusting Machine Learning in Nuclear Plant Control: A Reasoning-Based Discrepancy Checker. 12th Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2021). Retrieved from https://www.ans.org/pubs/proceedings/article-49752/