DARPAN KRISHNAKUMAR SHUKLA

Employment

Employment history is unavailable.

Education

• Homi Bhabha National Institute Doctor of Philosophy in Engineering
  2016 - 2022
• Pandit Deendayal Petroleum University Master of Technology in Nuclear Engineering
  2013 - 2015
• Gujarat Technological University Bachelors of Engineering in Electronics and Communication Engineering
  2009 - 2013

Projects & Funding

Projects & funding information is unavailable.

Publications (20)

• A hierarchy identification algorithm for traslation of high level models to low level models
  IGCM 2023 Indo-German conference on Computational Mathematics: Challenges and Opportunities, Indian Institute of Science, Bangalore, IN 2023
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• A Fan-Controlled Sodium-to-Air Heat Exchanger Configuration for Failsafe Decay Heat Removal in Sodium-Cooled Fast Reactors
  A. John Arul, Parthkumar Rajendrabhai Patel, Darpan Krishnakumar Shukla
  Nuclear Technology 2023 1 citation DOI: 10.1080/00295450.2023.2175584
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• An application of AI and BN techniques to the prediction of human error: A case study with SACADA database
  ENT 2023 International Interdisciplinary Conference on Energy, Nanotechnology and IOT, National Institute of Technology Puducherry, Karaikal, IN 2023
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• Study of Advanced Methods for Reliability Analysis of Digital I & C Systems
  2022
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• An efficient Dijkstra’s semaphore based k-out-of-n Petri net voting model: An application to shutdown actuation system reliability
  Annals of Nuclear Energy 2021 4 citations DOI: 10.1016/j.anucene.2021.108218
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• Study of Advanced Methods for Reliability Analysis of Digital I&C Systems
  Homi Bhabha National Institute 2021
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• Reliability analysis of a reconfigurable safety system using Petri Net and comparison with smart component method
  30th European Safety and Reliability Conference and 15th Probabilistic Safety Assessment and Management Conference (ESREL2020 PSAM15) 2020 0 citations DOI: 10.3850/978-981-14-8593-0_3981-cd
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• Static and dynamic reliability studies of a fast reactor shutdown system using smart component method
  Annals of Nuclear Energy 2020 9 citations DOI: 10.1016/j.anucene.2019.107011
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• A Review of Recent Dynamic Reliability Analysis Methods and a Proposal for a Smart Component Methodology
  Reliability, Safety and Hazard Assessment for Risk-Based Technologies 2020 10 citations DOI: 10.1007/978-981-13-9008-1_22
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• Automatic petri net generation from smart component reliability models
  Proceedings of the 30th European Safety and Reliability Conference and the 15th Probabilistic Safety Assessment and Management Conference 2020 0 citations DOI: 10.3850/978-981-14-8593-0_3992-cd
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• Modeling Inhomogeneous Markov Process in Smart Component Methodology
  Reliability, Safety and Hazard Assessment for Risk-Based Technologies 2020 1 citation DOI: 10.1007/978-981-13-9008-1_26
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• A smart component methodology for reliability analysis of dynamic systems
  Annals of Nuclear Energy 2019 10 citations DOI: 10.1016/j.anucene.2019.07.027
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• India-United States Collaboration on Advanced Dynamic Reliability Modeling
  16th Probabilistic Safety Assessment and Analysis (PSA) - American Nuclear Society 2019
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• India-United States collaboration on advanced dynamic reliability modeling
  PSA 2019 - International Topical Meeting on Probabilistic Safety Assessment and Analysis 2019
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• Reliability analysis of a safety system using Petri Net and comparison with smart component methodology
  PSA 2019 - International Topical Meeting on Probabilistic Safety Assessment and Analysis 2019
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• Inhomogeneous Markov process in Smart Component Methodology: Towards a general dynamic reliability method
  Research Scholars Meet on Materials Science and Engineering of Nuclear Materials-HBNI 2018
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• Development of Smart Component Based Framework for Dynamic Reliability Analysis of Nuclear Safety Systems
  International Atomic Energy Agency (IAEA) 2017
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• Dynamic System Reliability Estimation by Monte Carlo Simulation: Comparison with Markov and Fault Tree Models
  Indo-UK Workshop on Modeling and Simulation of Safety and Materials for Nuclear Application 2015
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• MCDP: Development of a code for neutronic calculations for homogeneous reactors
  Unpublished 2015 DOI: 10.13140/rg.2.1.3917.7208
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• Reactor Criticality Computations in Neutron Transport Theory Using Monte Carlo Method
  2015 DOI: 10.13140/rg.2.1.2592.4249/1
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