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

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

Computationally efficient fragility assessment using equivalent elastic limit state and Bayesian updating

Kwag, S., & Gupta, A. (2018), Computers and Structures, 197, 1–11. https://doi.org/10.1016/j.compstruc.2017.11.011

Probabilistic risk assessment based model validation method using Bayesian network

Kwag, S., Gupta, A., & Dinh, N. (2018), Reliability Engineering & System Safety, 169, 380–393. https://doi.org/10.1016/j.ress.2017.09.013

Seismic Fragility of Steel Piping System Based on Pipe Size, Coupling Type, and Wall Thickness

Ju, B. S., Gupta, A., & Ryu, Y. (2018), INTERNATIONAL JOURNAL OF STEEL STRUCTURES, 18(4), 1200–1209. https://doi.org/10.1007/s13296-018-0100-4

Simulation of constrained variables in engineering risk analyses

Tadinada, S. K., & Gupta, A. (2018), American Statistician, 72(2), 130–139. https://doi.org/10.1080/00031305.2016.1255660

Performance-based reliability of ASME piping design equations

Gupta, A., Saigal, R. K., & Ryu, Y. (2017), Journal of Pressure Vessel Technology, 139(3). https://doi.org/10.1115/1.4034584

Piping fragility evaluation: Interaction with high-rise building performance

Ju, B. S., Gupta, A., & Ryu, Y. H. (2017), Journal of Pressure Vessel Technology, 139(3). https://doi.org/10.1115/1.4034406

Probabilistic risk assessment framework for structural systems under multiple hazards using Bayesian statistics

Kwag, S., & Gupta, A. (2017), Nuclear Engineering and Design, 315, 20–34. https://doi.org/10.1016/j.nucengdes.2017.02.009

Structural fragility of T-joint connections in large-scale piping systems using equivalent elastic time-history simulations

Tadinada, S. K., & Gupta, A. (2017), Structural Safety, 65, 49–59. https://doi.org/10.1016/j.strusafe.2016.12.003

View all publications via NC State Libraries

Grants

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 - 9/30/19)

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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: 9/30/19

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 - 3/31/21)

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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: 3/31/21

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 - 12/31/20)

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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: 12/31/20

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 - 12/31/19)

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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: 12/31/19

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.

Close

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

Dominion Resources Services, Inc.(7/01/17 - 12/31/19)

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

Sponsor: Dominion Resources Services, Inc.

Start Date: 7/01/17

End Date: 12/31/19

Abstract

Full Membership

Close

Seismic Behavior and Fragility of Electrical Equipment, CNEFS Core Project

NCSU Center for Nuclear Energy Facilities and Structures (CNEFS)(1/01/17 - 12/31/19)

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Seismic Behavior and Fragility of Electrical Equipment, CNEFS Core Project

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

Start Date: 1/01/17

End Date: 12/31/19

Abstract

The objective of the proposed research is to use advanced modeling and simulation tools to determine if the nonlinearities in the mounting arrangement of the cabinets or building equipment interaction filter out the 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 vibration sensitive digital and electro-mechanical devices for the updated seismic hazard containing high frequency motions.

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CNEFS Administrative Account

NCSU Center for Nuclear Energy Facilities and Structures (CNEFS)(1/01/17 - 12/31/19)

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CNEFS Administrative Account

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

Start Date: 1/01/17

End Date: 12/31/19

Abstract

CNEFS Admin Account funded by Innose Tech 2017-0800

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Nondestructive Concrete Characterization System

US Army(12/20/16 - 3/29/19)

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Nondestructive Concrete Characterization System

Sponsor: US Army

Start Date: 12/20/16

End Date: 3/29/19

Abstract

Traditional concrete protective structures encountered by ground forces typically have unconfined compressive strengths of between 3,000 to 6,000 psi. Recent advances in concrete technology have resulted in new concrete materials with compressive strengths of 30,000 psi or greater. No field instrument currently exists that can simultaneously determine the compressive strength, thickness, and rebar configuration of concrete structures across today’s wide range of possible compressive strengths. In STTR Phase I/II efforts, NLA Diagnostics LLC (NLAD) developed a prototype instrument that measures both compressive strength and concrete thickness up to 33,000 psi and 6 ft, respectively. NLAD has also mapped out a technical course to locate rebar within the concrete. This proposed project will take input from military operators to improve packaging of the existing technology and to implement a rebar mapping capability in order to enhance military capabilities to defeat concrete protective structures, accelerate the ability to deploy concrete characterization instruments with operating forces, and reduce the technical risks associated with engaging concrete protective structures in tactical situations.

Close

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

Innose Tech Co., LTD(1/01/17 - 12/31/18)

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

Sponsor: Innose Tech Co., LTD

Start Date: 1/01/17

End Date: 12/31/18

Abstract

Full Membership

Close