Education

Research Description

Dr. Bourham's interests are in various areas with research diversity. Area of plasma science: he has interest in plasma-matter interactions, from interaction with solids to liquids to energetic combustible materials to fabrics and micro-organisms; and electrothermal plasmas for propulsion, thrusters and pellet injectors for fusion fueling. Area of materials synthesis and coatings: shielding and radiation attenuation studies, nuclear and mixed waste disposal, drycasks and high-level waste packaging, and evaluation of materials’ corrosion using electrochemical techniques.

Publications

Bi₂O₃-ZrO₂ Polymer Composites: Evaluation of Structural, Chemical, and γ-ray and Charged Particle Shielding Properties

Cao, D., Bourham, M., & Yang, G. (2024, July 2), ACS APPLIED ENGINEERING MATERIALS, Vol. 7. https://doi.org/10.1021/acsaenm.4c00337

Computational Evaluation on the Use of Some Selected Ceramic MAX-Phase Coatings as Shielding Layers on Spent Fuel Dry Cask Canisters

, (2023). IOSR Journal Of Applied Physics. Retrieved from https://www.iosrjournals.org/iosr-jap/papers/Vol15-issue1/Ser-1/B1501010516.pdf

Noninvasive liquid level sensing with laser generated ultrasonic waves

Kim, H., Balagopal, B., Kerrigan, S., Garcia, N., Chow, M.-Y., Bourham, M., … Jiang, X. (2023), Ultrasonics, 130, 106926. https://doi.org/10.1016/j.ultras.2023.106926

A theoretical study on the radiation shielding performance of borate and tellurite glasses

Alzahrani, J. S., Eke, C., Alrowaili, Z. A., Boukhris, I., Mutuwong, C., Bourham, M. A., & Al-Buriahi, M. S. (2022), Solid State Sciences, 129, 106902. https://doi.org/10.1016/j.solidstatesciences.2022.106902

An assessment of protective coating dry cask canisters with structurally amorphous metals (SAMs) for enhanced radiation shielding

Alsmadi, Z. Y., & Bourham, M. A. (2022), NUCLEAR ENGINEERING AND DESIGN, 388. https://doi.org/10.1016/j.nucengdes.2022.111647

Computational Investigation of Beryllium and Lithium Performance in Future Fusion Tokamaks

Elbasha, N. M., Bourham, M. A., & Mohamed, B. F. (2022), New Energy Exploitation and Application, 1(1). https://doi.org/10.54963/neea.v1i1.17

Shielding and corrosion properties of the Alloy 709 as canister material for spent nuclear fuel dry casks

Alsmadi, Z. Y., & Bourham, M. A. (2023), Defence Technology, 21, 116–124. https://doi.org/10.1016/j.dt.2022.08.002

Corrosion resistance and mechanical properties of Armakap cement for nuclear applications

Moneghan, D., Shkoukani, G., Eapen, J., Bourham, M., Mustafa, W., & Kilani, R. (2021), NUCLEAR ENGINEERING AND DESIGN, 374. https://doi.org/10.1016/j.nucengdes.2021.111049

Enhanced Shielding and Mechanical Properties of White Cement Mortars via Celestobarite Fine Aggregate

, (2021). International Journal of General Engineering and Technology. Retrieved from http://iaset.us/archives?jname=74_2&year=2021&submit=Search

Shielding Properties of 316 Stainless Steel with Multi-Layered Barriers for Spent Fuel Drycasks

, (2021). International Journal of Physics and Research, 11-1, 5–20. https://doi.org/10.24247/ijprjun20212

View all publications via NC State Libraries

Grants

Flexible Hard Ceramic Coatings by Ultrasonic Spray Mist-CVD for Dry Storage Canisters of Spent Nuclear Fuel and Waste

US Dept. of Energy (DOE)(10/01/20 - 9/30/24)

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Flexible Hard Ceramic Coatings by Ultrasonic Spray Mist-CVD for Dry Storage Canisters of Spent Nuclear Fuel and Waste

Sponsor: US Dept. of Energy (DOE)

Start Date: 10/01/20

End Date: 9/30/24

Abstract

The goal of the project is to develop and evaluate the use of ultrasonic spray mist chemical vapor deposition (Mist-CVD) manufacturing process for depositing high quality multi-component ceramic coatings (TiN, ZrO2, Al2O3, and MoS2), enabled by flexible sandwiched Zr-Si-O buffer layer, for enhancing the long term reliability of dry storage canisters (DSC). Such flexible ceramic coatings represent a new class of coatings, which are simultaneously hard, tough and resistant to cracking. This project aims at establishing a fundamental understanding of the composition-structure-property-performance relationship of these emerging flexible ceramic coatings materials to identify key factors that lead to their wide applications in DSC towards improved resistances to stress corrosion cracking (SCC), decay heat and hydrogen diffusion. The success of the project will generate crucial insights into the potential deployment of flexible hard ceramic coatings to enhance the reliability of long-term storage and maintenance of DSC.

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High Resolution Scanning Acoustic Microscopy System for High Throughput Characterization of Materials and Nuclear Fuels

US Dept. of Energy (DOE)(10/01/21 - 9/30/23)

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High Resolution Scanning Acoustic Microscopy System for High Throughput Characterization of Materials and Nuclear Fuels

Sponsor: US Dept. of Energy (DOE)

Start Date: 10/01/21

End Date: 9/30/23

Abstract

The goal of this NEUP infrastructure project is to acquire a state-of-the-art high resolution scanning acoustic microscopy system to enhance NCSU������������������s educational and research capabilities in high throughput characterization of nuclear fuels, nuclear sensor materials, cladding materials, reactor structural materials and 3D printed components.

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Enhancement of Material Characterization Capabilities at North Carolina State University

US Dept. of Energy (DOE)(10/01/19 - 9/30/22)

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Enhancement of Material Characterization Capabilities at North Carolina State University

Sponsor: US Dept. of Energy (DOE)

Start Date: 10/01/19

End Date: 9/30/22

Abstract

The objective of this project is to enhance research and educational infrastructure of Nuclear Engineering Program of North Carolina State University (NCSU) in material characterization/examination for supporting nuclear energy related studies.

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High Temperature Embedded/integrated Sensors (HITEIS) For Remote Monitoring Of Reactor And Fuel

US Dept. of Energy (DOE)(10/01/17 - 9/30/22)

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High Temperature Embedded/integrated Sensors (HITEIS) For Remote Monitoring Of Reactor And Fuel

Sponsor: US Dept. of Energy (DOE)

Start Date: 10/01/17

End Date: 9/30/22

Abstract

In this project, we will develop high temperature (> 600 C) embedded/integrated sensors (HiTEIS) for wireless monitoring of reactor and fuel cycle systems. HT pressure sensors, vibration sensors and liquid level sensors will be designed, fabricated, embedded and characterized, followed by nuclear structure integration and evaluations. The proposed technique will likely be used to enhance the safety and efficiency of nuclear power systems.

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Faculty Development Program in Nuclear Engineering at North Carolina State University, 2018

US Nuclear Regulatory Commission(7/30/19 - 7/29/22)

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Faculty Development Program in Nuclear Engineering at North Carolina State University, 2018

Sponsor: US Nuclear Regulatory Commission

Start Date: 7/30/19

End Date: 7/29/22

Abstract

The Department of Nuclear Engineering at North Carolina State University (NCSU) was previously awarded NRC faculty development grants, which have been extremely beneficial to the development and success of our tenure-track faculty to advance in their academic careers.

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Evaluation of the Performance of ArmaKap Ceramic Cement as a Radiation Shielding Materials with Experiments and Simulations

ArmaKap Technologies(9/01/17 - 12/31/20)

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Evaluation of the Performance of ArmaKap Ceramic Cement as a Radiation Shielding Materials with Experiments and Simulations

Sponsor: ArmaKap Technologies

Start Date: 9/01/17

End Date: 12/31/20

Abstract

ArmaKap Technologies developed Ceramic Cement as an innovative material that can be used for radiation shielding. Preliminary results on such materials have shown better attenuation of gamma rays as compared to conventional concrete mixes. Exposure to radiation comes from various sources such as cosmic rays, highly energetic radiation from outer space and terrestrial natural radiation. Natural radiation included naturally-radioactive elements. Additional radiation sources x-rays in medical facilities, nuclear reactors, nuclear weapons, cathode ray tubes used in TV and computer displays, and numerous other radiation-producing devices. Magnitude of the radiation dose in any radiation-producing facility, as well as natural sources, must be controlled to eliminate exposure to radiation, or to limit exposure to the regulatory standards. This proposal aims to conduct research on the ArmaKap ceramic cement to determine its gamma ray attenuation efficiency and its appropriateness for radiation shielding when used in nuclear and waste disposal facilities.

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Faculty Development Program in Nuclear Engineering at North Carolina State University, 2017

US Nuclear Regulatory Commission(6/30/17 - 6/29/20)

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Faculty Development Program in Nuclear Engineering at North Carolina State University, 2017

Sponsor: US Nuclear Regulatory Commission

Start Date: 6/30/17

End Date: 6/29/20

Abstract

NRC faculty development grants previously awarded to the Department of Nuclear Engineering at North Carolina State University (NCSU) have been extremely beneficial to the development and success of our tenure-track faculty to advance in their academic careers. We hired a new faculty in the area of nuclear materials and we are recruiting and interviewing new entry-level faculty in one of the respective areas of dosimetry and nuclear assay, fission power reactors, thermal hydraulics, and related subjects. The NRC faculty development program will help us supporting the newly hired faculty and the r4ecruiting of new faculty by encouraging recently graduated PhDs of the highest caliber to apply to our program. Upon hiring, and with the NRC award plus what we provide as a startup package, the hired junior faculty will be supported and helped to establish their academic career with the help of the senior faculty mentorship. A measure of the NRC faculty development award will be realized when the tenure-track faculty successfully advances towards tenure and promotion to higher ranks, and earning a reputation within the nuclear engineering institutions. For our department of nuclear engineering, it is a great benefit to hire top talent young faculty in the open positions and to retain recently hired tenure-track faculty with our expansion in all nuclear engineering main thrust research areas.

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Advanced Nuclear Materials Laboratory Enhancements for Corrosion and Stress Corrosion Testing

US Dept. of Energy (DOE)(10/01/17 - 9/30/19)

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Advanced Nuclear Materials Laboratory Enhancements for Corrosion and Stress Corrosion Testing

Sponsor: US Dept. of Energy (DOE)

Start Date: 10/01/17

End Date: 9/30/19

Abstract

Funding is requested, through the DOE NEUP Infrastructure program, to obtain the acquisition of autoclaves and equipment for Corrosion, Stress-assisted Corrosion, and Stress Corrosion Cracking testing of nuclear materials for structural and cladding applications in LWRs, and corrosion studies related to HLW storage packages. The proposed equipment and laboratory enhancements will be used in the performance of research related to existing DOE projects and proposed efforts in the areas of advanced nuclear fuels and materials. The equipment will also be used for the purpose of a laboratory class which is being developed by the PIs for inclusion in the curriculum. The 1 credit Lab is in complement to the 3 credit Nuclear Materials Science class. It will also be of relevance for a class on Corrosion of Nuclear Materials developed by two of the co-PIs at the graduate level which will cover issues related to corrosion and stress corrosion of materials used in nuclear reactors. Henceforward, the requested infrastructure will also enable/enhance the Teaching/Learning Mission of the NE department at NCSU.

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North Carolina State University GAANN Interdisciplinary Doctoral Program in Nuclear Science and Engineering

US Dept. of Education (DED)(9/01/15 - 8/31/19)

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North Carolina State University GAANN Interdisciplinary Doctoral Program in Nuclear Science and Engineering

Sponsor: US Dept. of Education (DED)

Start Date: 9/01/15

End Date: 8/31/19

Abstract

North Carolina State University proposes to increase its commitment to graduate training in nuclear science and engineering, an interdisciplinary field comprising two areas critical to national need: Physics and Engineering. The goal of this proposal is to enlarge the pool of U.S. citizens and permanent residents who will pursue teaching and research careers in nuclear science and engineering, thereby promoting workforce development and technological innovation impacting human health, national security, energy security, and environmental sustainability. The general program objectives for the three-year budget period are as follows: ��������������� Recruit six GAANN doctoral fellows, including women, minorities and persons with disabilities, to NC State������������������s program in nuclear science and engineering. ��������������� Ensure that GAANN fellows benefit from available world-class resources in nuclear science and engineering, obtain doctoral degrees, and find suitable employment. Anticipated program outcomes are the following: ��������������� Six additional Ph.D. scientists or engineers with nuclear science and engineering expertise, interdisciplinary team experience, enhanced skills and experience in instructional techniques, and professional development training. ��������������� Post-doctoral employment in research or teaching positions for all GAANN fellows, contributing to greater diversity among the nation������������������s research and education workforce. ��������������� Enhanced interdisciplinary focus on nuclear science and engineering at NC State through recruiting outstanding students interested in teaching and/or research careers.

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Ablation Studies of Plasma-Facing Materials due to Edge Localized Modes and Hard Disruptions in Tokamak Fusion Reactors

US Dept. of Energy (DOE)(3/01/16 - 1/31/19)

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Ablation Studies of Plasma-Facing Materials due to Edge Localized Modes and Hard Disruptions in Tokamak Fusion Reactors

Sponsor: US Dept. of Energy (DOE)

Start Date: 3/01/16

End Date: 1/31/19

Abstract

Plasma facing components (PFC) in tokamak fusion reactors like ITER are subject to high heat fluxes following thermal quench phases, disruption severity and edge localized modes (ELM), where PFCs can suffer from serious surface erosion and deterioration. Heat fluxes of to several GW/m2 over a short time of 0.1-1.0ms are expected, which may evaporate the PFC surface, including possible melt-layer erosion of metallic surfaces such as tungsten and molybdenum. This proposal has the objective of conducting experiments to expose selected PFC materials to induced disruptions and ELMs within the General Atomics National Fusion Facility DIII-D tokamak under joint collaboration between Oak Ridge national Lab (ORNL) and DIII-D. Tungsten alternative PFCs of interest to ORNL and DIII-D will be investigated, including mono and polycrystalline silicon carbide and new max-phase ceramics. Material samples will be installed on the Divertor Materials Evaluation System (DiMES) on the DIII-D tokamak to measure their erosion when exposed to the induced controlled ELMs with diagnostics.

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