Nuclear Engineering

College of Engineering

Works Published in 2019

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Displaying works 1 - 20 of 113 in total

Sorted by most recent date added to the index first, which may not be the same as publication date order.

2019 conference paper

Model-based resilience assessment framework for autonomous systems

ASME International Mechanical Engineering Congress and Exposition, Proceedings (IMECE), 13.

By: M. Diaconeasa, A. Mosleh*, A. Morozov* & A. Tai*

Source: ORCID
Added: March 3, 2022

2019 conference paper

A numerical and experimental study supporting a methodology for live monitoring, leak detection, and automatic response in water pipelines

ASME International Mechanical Engineering Congress and Exposition, Proceedings (IMECE), 13.

By: W. Chalgham*, M. Diaconeasa, R. Gottumukkala* & A. Seibi*

Source: ORCID
Added: March 3, 2022

2019 conference paper

A dynamic pipeline network health assessment software platform for optimal risk-based prioritization of inspection, structural health monitoring, and proactive management

ASME International Mechanical Engineering Congress and Exposition, Proceedings (IMECE), 13.

By: W. Chalgham*, M. Diaconeasa, K. Wu* & A. Mosleh*

Source: ORCID
Added: March 3, 2022

2019 conference paper

A smart pipeline monitoring and emergency response system using web services

ASME International Mechanical Engineering Congress and Exposition, Proceedings (IMECE), 13.

By: W. Chalgham*, M. Diaconeasa, K. Elgazzar* & A. Seibi*

Source: ORCID
Added: March 3, 2022

2019 journal article

Retrospective uranium enrichment potential using solid state dosimetry techniques on ubiquitous building materials

Journal of Nuclear Material Management, 47(2), 4–12.

By: R. Hayes

Source: NC State University Libraries
Added: November 6, 2020

2019 conference paper

Demonstration of a data-driven approach for error estimation in two-phase flow simulation using coarse-mesh CFD

Transactions of the American Nuclear Society, 121, 1865–1868.

By: H. Bao, J. Feng, H. Zhang & N. Dinh

Source: ORCID
Added: October 19, 2020

2019 article

Fracture Mechanics-Based Study of Stress Corrosion Cracking of SS304 Dry Storage Canister for Spent Nuclear Fuel

TMS 2019 148TH ANNUAL MEETING & EXHIBITION SUPPLEMENTAL PROCEEDINGS, pp. 1089–1097.

By: L. Tjayadi n, N. Kumar & K. Murty

Source: Web Of Science
Added: October 5, 2020

2019 journal article

The life and the contribution of B. R. Sehgal, G. Yadigaroglu and G. Hewitt: Remembrance statements

Nuclear Engineering and Design, 354.

By: N. Aksan, M. Andreani, S. Bechta, M. Corradini, F. D’Auria, V. Dhir, W. Frid, J. Jones ...

Source: ORCID
Added: July 28, 2020

2019 journal article

Validation and Uncertainty Quantification for Wall Boiling Closure Relations in Multiphase-CFD Solver

Nuclear Science and Engineering, 193(1-2), 81–99.

By: Y. Liu n & N. Dinh

Source: ORCID
Added: July 28, 2020

2019 conference paper

An artificial intelligence-guided decision support system for the nuclear power plant management

18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 394–406. http://www.scopus.com/inward/record.url?eid=2-s2.0-85073712176&partnerID=MN8TOARS

By: B. Hanna, T. Son & N. Dinh

Source: ORCID
Added: July 28, 2020

2019 conference paper

Uncertainty quantification and reduction for multiphase-CFD solvers: A data-driven Bayesian approach supported by high-resolution local measurements

18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 3582–3597. http://www.scopus.com/inward/record.url?eid=2-s2.0-85073755203&partnerID=MN8TOARS

By: Y. Liu, X. Sun, Y. Liu & N. Dinh

Source: ORCID
Added: July 28, 2020

2019 conference paper

Reynolds-averaged turbulence modeling using deep learning with local flow features

18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 1698–1711. http://www.scopus.com/inward/record.url?eid=2-s2.0-85073713566&partnerID=MN8TOARS

By: C. Chang, J. Fang & N. Dinh

Source: ORCID
Added: July 28, 2020

2019 conference paper

Development of a data-driven turbulence model for 3D thermal stratification simulation during reactor transients

18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 2223–2234. http://www.scopus.com/inward/record.url?eid=2-s2.0-85073734574&partnerID=MN8TOARS

By: Y. Zhu, N. Dinh, R. Hu & A. Kraus

Source: ORCID
Added: July 28, 2020

2019 conference paper

Assessment of smoothed particle hydrodynamics methods for simulating the external-flooding scenario

18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 981–992. http://www.scopus.com/inward/record.url?eid=2-s2.0-85073736251&partnerID=MN8TOARS

By: L. Lin, N. Dinh, S. Prescott, H. Bao, N. Montanari & R. Sampath

Source: ORCID
Added: July 28, 2020

2019 conference paper

A data-driven approach to scale bridging in system thermal-hydraulic simulation

18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 6069–6082. http://www.scopus.com/inward/record.url?eid=2-s2.0-85073761938&partnerID=MN8TOARS

By: H. Bao, R. Youngblood, H. Zhang, N. Dinh, L. Lin & J. Lane

Source: ORCID
Added: July 28, 2020

2019 journal article

DIII-D research towards establishing the scientific basis for future fusion reactors

NUCLEAR FUSION, 59(11).

By: C. Petty*, L. Abadie, T. Abrams, J. Ahn, T. Akiyama, P. Aleynikov, J. Allcock, E. Allen ...

Source: Web Of Science
Added: April 20, 2020

2019 journal article

A new cryogenic apparatus to search for the neutron electric dipole moment

JOURNAL OF INSTRUMENTATION, 14.

By: M. Ahmed*, R. Alarcon*, A. Aleksandrova*, S. Baessler*, L. Barron-Palos*, L. Bartoszek, D. Beck*, M. Behzadipour* ...

Source: Web Of Science
Added: February 3, 2020

2019 journal article

Application and Evaluation of Surrogate Models for Radiation Source Search

ALGORITHMS, 12(12).

By: J. Cook, R. Smith, J. Hite, R. Stefanescu & J. Mattingly

Source: Web Of Science
Added: January 21, 2020

2019 journal article

Influence of annealing parameters on the mechanical properties of heterogeneous lamella structured 5083 aluminum alloy

LETTERS ON MATERIALS, 9(4), 556–560.

By: X. Fang, G. He n, M. Ruiz n, C. Zheng, Y. Wang n, Z. Li, Y. Zhu

Source: Web Of Science
Added: December 30, 2019

2019 conference paper

Opportunities for a graded approach in air sample assay and triage

41st ESARDA Annual Meeting symposium on safeguards and nuclear material management. Presented at the 41st ESARDA Annual Meeting, Stressa, Italy.

By: R. Hayes, R. O’Mara & F. Abdelrahman

Event: 41st ESARDA Annual Meeting at Stressa, Italy on May 14-16, 2019

Sources: NC State University Libraries, ORCID
Added: December 16, 2019