Education

Research Description

Gupta is interested in modeling experimental and analytical behavior of structures, Nonclassically damped primary-secondary systems, Earthquake behavior of electrical instruments and control panels, Buried pipelines, Computer aided engineering.

Publications

A Closed-Form Solution to Characterize the Behavior of Piping T-Joints

Dubey, A. R., Gupta, A., & Cho, S. G. (2021, July 10), INTERNATIONAL JOURNAL OF STEEL STRUCTURES. https://doi.org/10.1007/s13296-021-00511-z

Seismic response of electrical equipment subjected to high?frequency ground motions

Singh, S., & Gupta, A. (2021), NUCLEAR ENGINEERING AND DESIGN, 374. https://doi.org/10.1016/j.nucengdes.2020.111046

Significance of multi-hazard risk in design of buildings under earthquake and wind loads

Kwag, S., Gupta, A., Baugh, J., & Kim, H.-S. (2021), ENGINEERING STRUCTURES. https://doi.org/10.1016/j.engstruct.2021.112623

A Bayesian Inference driven computational framework for seismic risk assessment using large-scale nonlinear finite element analyses

Tadinada, S. K., & Gupta, A. (2020), PROGRESS IN NUCLEAR ENERGY, 130. https://doi.org/10.1016/j.pnucene.2020.103556

A Framework for Simulation-Based Internal Flooding Risk Assessment

Dubey, A. R., Gupta, A., & Coleman, J. (2020), JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 142(1). https://doi.org/10.1115/1.4045028

Characterization of Limit State for Seismic Fragility Assessment of T-Joints in Piping System

Dubey, A. R., Gupta, A., & Cho, S. G. (2020), JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 142(5). https://doi.org/10.1115/1.4047041

Limitations of traditional tools for beyond design basis external hazard PRA

Vaishanav, P., Gupta, A., & Bodda, S. S. (2020), NUCLEAR ENGINEERING AND DESIGN, 370. https://doi.org/10.1016/j.nucengdes.2020.110899

Risk informed validation framework for external flooding scenario

Bodda, S. S., Gupta, A., & Dinh, N. (2020), NUCLEAR ENGINEERING AND DESIGN, 356. https://doi.org/10.1016/j.nucengdes.2019.110377

Current state of in-cabinet response spectra for seismic qualification of equipment in nuclear power plants

Gupta, A., Cho, S.-G., Hong, K.-J., & Han, M. (2019), NUCLEAR ENGINEERING AND DESIGN, 343, 269–275. https://doi.org/10.1016/j.nucengdes.2018.12.017

Fragility Evaluation in Building-Piping Systems: Effect of Piping Interaction With Buildings

Ryu, Y. H., Gupta, A., & Ju, B. S. (2019), JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 141(1). https://doi.org/10.1115/1.4039004

View all publications via NC State Libraries

Grants

Development and Assessment of Digital Twin for Advanced Reactors

US Dept. of Energy (DOE)(8/16/21 - 6/30/24)

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Development and Assessment of Digital Twin for Advanced Reactors

Sponsor: US Dept. of Energy (DOE)

Start Date: 8/16/21

End Date: 6/30/24

Abstract

A DT-DAP (Digital Twin Development and Assessment Process) methodology has been formulated at NCSU in the ARPA-E sponsored project. DT-DAP can be very effective in guiding the design, training, testing, and application of DTs to improve effectiveness, accuracy and acceptance of system design and safety analysis.

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Probabilistic Risk-Informed Approaches in Structural and Earthquake Engineering, CNEFS Enhancement Project

Electricite de France (EDF/DER)(1/01/20 - 12/31/21)

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Probabilistic Risk-Informed Approaches in Structural and Earthquake Engineering, CNEFS Enhancement Project

Sponsor: Electricite de France (EDF/DER)

Start Date: 1/01/20

End Date: 12/31/21

Abstract

In recent years, flooding at nuclear power plants (NPP) has increased emphasis on using high fidelity simulations to evaluate the vulnerability of nuclear plants. One of the key limitations in the use of high fidelity simulations is related to a lack of verification and validation (V&V) of such simulations. One outcome of incomplete and insufficient V&V relates to a large degree of uncertainty in the simulation results which in turn leads to conservative assumptions by the decision makers. Past experience has shown that such conservative assumptions in the context of safety assessment for other external hazards such as seismic have resulted in highly overdesigned NPP systems and excessively high costs. Therefore, it is quite important that various uncertainties in this process are appropriately identified and included through formal uncertainty quantification (UQ). A robust framework for verification and validation is needed to not only include uncertainties but also to formalize the confidence in predictions of system level validation that are based on component level data using Bayesian Network. In addition, the framework has to identify the basic events that are critical in the perspective of overall validation. This process helps in allocating the resources efficiently thereby reducing the effort to conduct high fidelity simulations and large-scale experiments.

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Probabilistic Risk-Informed Approaches in Structural and Earthquake Engineering, CNEFS Core Project

NCSU Center for Nuclear Energy Facilities and Structures (CNEFS)(3/01/20 - 12/31/20)

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Probabilistic Risk-Informed Approaches in Structural and Earthquake Engineering, CNEFS Core Project

Sponsor: NCSU Center for Nuclear Energy Facilities and Structures (CNEFS)

Start Date: 3/01/20

End Date: 12/31/20

Abstract

In recent years, flooding at nuclear power plants (NPP) has increased emphasis on using high fidelity simulations to evaluate the vulnerability of nuclear plants. One of the key limitations in the use of high fidelity simulations is related to a lack of verification and validation (V&V) of such simulations. One outcome of incomplete and insufficient V&V relates to a large degree of uncertainty in the simulation results which in turn leads to conservative assumptions by the decision makers. Past experience has shown that such conservative assumptions in the context of safety assessment for other external hazards such as seismic have resulted in highly overdesigned NPP systems and excessively high costs. Therefore, it is quite important that various uncertainties in this process are appropriately identified and included through formal uncertainty quantification (UQ). A robust framework for verification and validation is needed to not only include uncertainties but also to formalize the confidence in predictions of system level validation that are based on component level data using Bayesian Network. In addition, the framework has to identify the basic events that are critical in the perspective of overall validation. This process helps in allocating the resources efficiently thereby reducing the effort to conduct high fidelity simulations and large-scale experiments.

Close

Membership in the Center for Nuclear Energy Facilities and Structures (CNEFS), Full Member

Korea Atomic Energy Research Institute (KAERI)(1/01/20 - 12/31/21)

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Membership in the Center for Nuclear Energy Facilities and Structures (CNEFS), Full Member

Sponsor: Korea Atomic Energy Research Institute (KAERI)

Start Date: 1/01/20

End Date: 12/31/21

Abstract

The Center for Nuclear Energy Facilities & Structures, has been established and is administered by North Carolina State University to conduct research in the areas of structural engineering, mechanics, risk assessment, hazard mitigation, and construction engineering and to promote research, education, and training in the Research Area. The CENTER has developed core research, non-core research, and technology transfer activities.

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Probabilistic Risk Assessment Modeling Using MASTADON

US Dept. of Energy (DOE)(11/15/19 - 3/31/23)

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Probabilistic Risk Assessment Modeling Using MASTADON

Sponsor: US Dept. of Energy (DOE)

Start Date: 11/15/19

End Date: 3/31/23

Abstract

The proposed project builds upon the previous work of CNEFS in which CNEFS helped develop capabilities for Fault Tree Analysis in the Idaho National Lab (INL)’s MASTADON toolkit. The proposed project focuses on the following specific tasks • Extend the fault-tree analysis and quantification to include event-trees • Convert C++ code to MOOSE objects and implement in MASTODON. • Create examples for PRA in MASTODON using the new fault-tree and event-tree quantification implementations • Benchmark examples with Saphire • Document these examples on the MASTODON website

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Membership in Center for Nuclear Energy Facilities and Structures (CNEFS), Full Member

Korea Hydro & Nuclear Power Co., Ltd. (KHNP)(1/01/19 - 12/31/21)

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Membership in Center for Nuclear Energy Facilities and Structures (CNEFS), Full Member

Sponsor: Korea Hydro & Nuclear Power Co., Ltd. (KHNP)

Start Date: 1/01/19

End Date: 12/31/21

Abstract

Full Membership

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BIM for VTR: Holistic Approach to Design and Construction

US Dept. of Energy (DOE)(9/17/18 - 9/30/21)

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BIM for VTR: Holistic Approach to Design and Construction

Sponsor: US Dept. of Energy (DOE)

Start Date: 9/17/18

End Date: 9/30/21

Abstract

Huge escalations in overnight construction costs and schedule delays have rendered nuclear energy commercially unattractive. Much of the research and development has focused on developing new reactor designs with accident tolerant fuels and passive safety systems intended to reduce operating and lifecycle costs. There has been little to no investment in research on nuclear construction management. Moreover, Hopf [1] argues that the primary reasons for construction cost escalation and schedule delays are related to: (i) extremely stringent nuclear safety and quality assurance standards, (ii) inexperience in managing and staffing to nuclear QA standards, (iii) excessive paperwork, and (iv) supply chain delays due to rework. To ensure the success of implementation and deployment of a new reactor (i.e., Versatile Test Reactor (VTR)), design, construction, and testing processes should be integrated. Virtual Design and Construction (VDC) using Building Information Modeling (BIM) has been proven to be a solution that bridges gap between design and construction [cite]. Furthermore, it has been used as a project control tool [cite]. BIM as a central hub of digital data exchange can bring different experts (i.e., engineers with different disciplines and contractors who build and manage construction projects) virtually together. All stakeholders have a shared resources of knowledge to help identify and minimize risk during design, construction, and operation and maintenance phases [cite]. This proposal proposes to investigate and help INL better understand the capabilities of BIM that can support the integration of design, construction, and testing of the VTR. Furthermore, the research team will pick one of the analysis (i.e., pipe stress) and develop a software/plug-in that produces 2D/3D models that can be directed imported by the analysis tool.

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DEVELOPMENT OF A NEARLY AUTONOMOUS MANAGEMENT AND CONTROL SYSTEM FOR ADVANCED REACTORS

US Dept. of Energy (DOE) - Advanced Research Projects Agency - Energy (ARPA-E)(10/01/18 - 9/30/21)

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DEVELOPMENT OF A NEARLY AUTONOMOUS MANAGEMENT AND CONTROL SYSTEM FOR ADVANCED REACTORS

Sponsor: US Dept. of Energy (DOE) - Advanced Research Projects Agency - Energy (ARPA-E)

Start Date: 10/01/18

End Date: 9/30/21

Abstract

The proposed project seeks to establish a technical basis for, and preliminary development of, a Nearly Autonomous Management and Control (NAMAC) system in advanced reactors. The system is intended to provide recommendations to operators during all modes of plant operation except shutdown operations: plant evolutions ranging from normal operation to accident management. These recommendations are to be derived within a modern, artificial-intelligence (AI) guided system, making use of continuous extensive monitoring of plant status, knowledge of current component status, and plant parameter trends; the system will continuously predict near-term evolution of the plant state, and recommend a course of action to plant personnel.

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Center for Nuclear Energy Facilities & Structures, Full Member

Electricite de France (EDF/DER)(1/01/18 - 12/31/23)

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Center for Nuclear Energy Facilities & Structures, Full Member

Sponsor: Electricite de France (EDF/DER)

Start Date: 1/01/18

End Date: 12/31/23

Abstract

Full Membership

Close

Effect of High Frequency Ground Motions on Seismic Fragility of Equipment and Piping, CNEFS Core Project

NCSU Center for Nuclear Energy Facilities and Structures (CNEFS)(7/01/17 - 12/31/20)

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Effect of High Frequency Ground Motions on Seismic Fragility of Equipment and Piping, CNEFS Core Project

Sponsor: NCSU Center for Nuclear Energy Facilities and Structures (CNEFS)

Start Date: 7/01/17

End Date: 12/31/20

Abstract

The objective of the proposed research is to use advanced modeling and simulation tools to determine if the building-equipment interaction help in reduction of response of secondary systems when subjected to high frequency motions. The motivation for conducting the proposed research is driven by the anticipated savings in the enormous effort and cost that is currently faced by the nuclear industry in attempting to qualify equipment, piping, and structures for the updated seismic hazard containing high frequency motions.

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