Nuclear Engineering

The Nuclear Engineering program is offered under the department of Nuclear Engineering and Radiation Science (NERS).  The primary mission of the NE program is to provide an outstanding and comprehensive education to tomorrow's leaders in nuclear science and technology. Nuclear Engineering is a strong and growing engineering program administered by highly motivated and active nuclear engineering faculty.

The educational objectives for graduate degrees in Nuclear Engineering are:

1. Graduates will apply subject matter knowledge within their field of study.
2. Graduates will communicate effectively, both orally and in writing.
3. Graduates will engage in productive analysis and criticism of their own and others' research.
4. Graduates will demonstrate the ability to further develop as a professional in their field.

There are a number of research laboratories and facilities available for graduate students:

The Missouri S&T Reactor (MSTR) is located on the Missouri University of Science and Technology campus in Rolla, Missouri.  MSTR provides facilities for experimental research, undergraduate training, and learning about reactor physics and other aspects of nuclear engineering.  It is a 200 kW pool-type reactor, and is integral to the education of Nuclear Engineering students through hands-on laboratory activities.  The reactor was initially licensed in 1961, and was converted from high-enriched uranium (HEU) to low-enriched uranium (LEU) in 1992.  Recently MSTR has gone through a number of changes.  A new active cooling system capable of removing up to 400 kW of heat was installed using funding from the Department of Energy in 2013.  In 2014 new digital control room systems were installed, replacing the original systems from 1961 and allowing MSTR to serve as a testbed for a new digital reactor control technologies.  A distance education system, also installed in 2014, allows our faculty and staff to provide online training through distance education for students around the world.  Additional modifications are planned over the next several years, including the installation of new digital recording systems to replace paper records.  Research facilities, experimental capabilities and services available at the reactor include:

• A neutron beam port for neutron radiography, tomography and ex-core neutron irradiations
• Thermal column for experiments involving thermal neutrons
• Pneumatic transfer tubes for in-core irradiation experiments and Neutron Activation Analysis (NAA)
• Isotope production elements and void tubes for in-core irradiations
• Internet accessible hot cell facility for high-activity sample irradiation and counting
• Subcritical assembly for teaching the fundamentals for reactor physics
• Gamma spectroscopy systems equipped with Sodium-Iodide (NaI) and High Purity Germanium (HPGe) detectors
• Liquid scintillation counter for alpha and beta spectroscopy
• State-of-the-art distance education system for broadcasting reactor labs to outside universities and organizations

Radiation imaging has been the most successful and useful method of early cancer detection as well as highly helpful nondestructive testing method for various industrial applications.  In the Advanced Radiography and Tomograph Laboratory (ARTLAB), we are developing innovative radiation imaging systems for medical and industrial purposes.  We develop and utilize a wide range of new tools, from x-ray sources for radiation imaging to sophisticated algorithms for image processing and computed tomography (CT) reconstruction.  One such example is the ongoing project of developing a stationary CT, a new type of x-ray tubes for fast imaging is under development.  Also, we develop machine learning algorithms for radiation image analysis and automatic radiosotope detection for homeland security and defense applications.  The lab is equipped with a homemade benchtop 3D CT, a clean room for x-ray tube experiments and a high-performance computer server with COMSOL software for simulation studies.

The D-D generator laboratory uses Deuterium gas and a microwave to generate plasma as an ion source to induce nuclear fusion.  This results in a relatively high-flux source of fast and epithermal neutrons useful for prompt gamma neutron activation analysis, neutron activation analysis, and radiography.  Using Deuterium rather than radioactive Tritium, as well as an “open-vacuum” construction, allows the system to be easily reconfigured for experiments.

The Thermal Hydraulic Experiment, Modeling, and Engineering Simulation (THEMES) Laboratory is designed as a modular, multipurpose facility capable of supporting a wide variety of multiphase flow experiments, simulations, and modeling efforts.  The central feature of the THEMES Laboratory is a modular test facility designed to support up to six concurrent experiments by effectively utilizing existing infrastructure.  This allows for rapid deployment of experiments, lets projects to progress rapidly to the construction and testing phases, and reduces the cost to the sponsor. A 30 hp pump provides up to 1000 gpm of water flow at 90 ft of head, while a 50 hp compressor provides up to 270 acfm of compressed air at a pressure of 200 psi.  Flow is measured using pressure transducers, rotameters, a laminar flow element, a vortex flow meter, a magnetic flow meter, and other state-of-the-art instruments.  Robust four-sensor electrical conductivity probes for multiphase flow measurements are constructed and characterized in-house, with unique software for enhancing data processing performance.

The Vacuum Technology and X-Ray Generation Laboratory is located in Fulton 213 and has facilities to produce and work with vacuum technology up to 10^-9 Torr. The equipment includes roughing mechanical pumps, ion pumps, turbo pumps, glass vacuum chambers, steel vacuum chambers with programmable ramp-heating capabilities, Residual Gas Analyzer-RGA200, and a variety of pressure gauges, ion guns, and radiation detectors and other measurement equipment. Total area is 561 sq ft.

The Radiochemistry and Nanotechnology Laboratory is located in Fulton 218 and houses a fume hood with wet chemistry capabilities, a two seat glove box, chemical waste disposal, safes for radioactive materials, UV-Vis Spectrophotometer, analytical balance, centrifuges, vacuum filtration and drying system, furnace, stereo microscope, ultrasonicators, with a total area of 466 sq. ft.

The Nuclear Materials Laboratory is home to two lab facilities with specialized equipment for characterizing the effects of radiation on solids at the atomic and microscopic scales. Equipment available includes a Confocal Raman Microscope, a Positron Annihilation Lifetime Spectrometer, a Modulated Photothermal Radiometer, a Three-Omega system configured for thermal diffusivity measurements and a Four-Terminal Resistivity Station. The facilities of the campus Materials Research Center are also available for nuclear materials related research. These facilities include state-of-the-art Scanning and Transmission Electron Microscopes, X-ray Diffractometers, a Nanoindenter, Atomic Force Microscope and X-Ray Photoelectron Spectrometer among other tools. Ample opportunities exist for Nuclear Engineering students to collaborate with students and researchers in the campus Materials Science and Engineering Department.

The Radiation Measurements and Spectroscopy Laboratory is a teaching lab mainly for education and training of undergraduate nuclear engineering students. Three identical workstations for alpha particle, beta particle, and gamma-ray spectroscopy can provide “hands-on” training in radiation detection and measurement for 18 students at a time. The five internet-accessible digital signal analyzers allow 50 remote users to participate in nuclear spectroscopy and measurement and collection of spectra data via an internet connection at any given time. When the RMSL is not in use for education or training, it is open for faculty and graduate students to conduct research. The lab was significantly renovated with support from DOE and is equipped with state-of-the-art radiation detectors and signal processing systems.

The Nuclear Engineering Program offers both a thesis-based and non-thesis MS degree program.  A B.S. in a related field of engineering or suitable physical science is a prerequisite for admission in to the Nuclear Engineering graduate program.  The M.S. degree program is designed to provide training and expertise in the design of nuclear energy systems, as well as the use of nuclear technology in medical and industrial applications.

Some exposure to research is considered an essential component of the MS program, so the non-thesis option is intended for students with significant industrial experience (more than 3 years) and is not encouraged for other students.  Students should plan to complete their MS program in two to four semesters. A MS program requires a minimum of 30 credit-hours of research and coursework.  A minimum of six credits of 6000-level courses must be included (nine credits for a non-thesis option), and at most three credits of 3000-level courses.  Students are encouraged to take at least six credits of courses outside of their program. For a thesis option, at least 6 credits of graduate research and at least 18 credits of lecture courses are required as part of the 30 credit-hours.

The ‘core’ Nuclear Engineering courses are NUC ENG 5203 (Reactor Physics I), 5241 (Nuclear Materials I), 5257 (Introduction to Nuclear Thermal Hydraulics), and 5312 (Nuclear Radiation Measurements and Spectroscopy).  These courses address key competencies that all Nuclear Engineers should possess.  Students who completed these courses or their equivalent during an undergraduate Nuclear Engineering degree need not take the courses again, however students with undergraduate degrees from other disciplines should take NUC ENG 3205 (Fundamentals of Nuclear Engineering) in addition to these core courses.  Students are also encouraged to take at least 3 credits of graduate level mathematics or computer science. A maximum of nine credit-hours of graduate level courses taken elsewhere as a graduate student can be transferred to the MS plan of study, provided that the courses correspond to at least a 5000-level course at Missouri S&T.

The Doctor of Philosophy (PhD) program is open to students who have successfully completed their MS program or have enrolled in a direct PhD program.  It is designed to provide additional training and expertise in the design of nuclear energy systems and the use of nuclear technology in medical and industrial applications, with a strong focus on engineering research.

Typically a minimum of 5 semesters (not including summer sessions) is required to complete the program for students arriving with a MS degree, and a minimum of 7 semesters for students starting a direct PhD program.  The doctoral program will include at least 72 credit hours of total coursework.  Students who already hold a Master's degree will receive a block of 30 credit hours that will apply toward that requirement.  They must complete an additional 42 hours of graduate credit.  A minimum of 12 credit hours must be lecture courses, and a minimum of 24 credit hours must be graduate research.  It is recommended that nine of the 12 credit hours of lecture courses come from 6000-level lecture courses.  A student who does not hold a Master's degree must complete a minimum of 30 credit hours of lecture courses and at least 24 credit hours of graduate research.  At least 15 credit hours should be in 6000-level lecture courses.  Students are also encouraged to enroll in at least six credits of advanced mathematics or computer science courses.

PhD candidates must also complete a qualifying examination within their first four semesters of study, comprehensive examination when at least 50% of their coursework is completed, and final examination where they will present and defend the research included in their dissertation.

There is a residency requirement for the PhD in Nuclear Engineering. Residency at Missouri S&T is defined as sustained intellectual interactions among the student and the academic community.  The candidate for a Ph.D. degree will normally complete three years of residency, which is the equivalent of completing six academic semesters while enrolled as an on-campus student at Missouri S&T.  Students holding a master’s degree are automatically credited with two semesters of residency. Students unable to meet the residency requirement given above, such as distance students, can meet this requirement through an alternative route in consultation with their advisor.

Nuclear Nonproliferation

The nuclear engineering program offers a graduate certificate program to professionals and students who desire to undergo formal instruction in nuclear nonproliferation.  The topics in comprising the certificate program are selected from courses available to graduate students in the nuclear engineering program at Missouri University of Science and Technology.  All courses are available both in traditional on-campus delivery and online format.  The certificate program deployment strategy allows all enrollees to pace their study in manner consistent with the individual’s plans.

The Graduate Certificate in Nuclear Nonproliferation is open to all persons holding a B.S., M.S., or Ph.D. degree in Engineering, Science, and/or Mathematics as well as related B.A. or M.A. degrees, or are currently accepted into a graduate degree program at Missouri S&T. 

Curriculum

The certificate program requires 4 courses equivalent to 12 credit hours.  There are 8 course available to the certificate program, 1 of which is required for the completion of the graduate certificate in nuclear nonproliferation.  Program enrollees may select any 3 of the remaining 7 courses towards the completion of the graduate certificate.  Enrollees may take 1 or 2 classes each semester so that the certificate program may be completed within 1 to 2 years.

Required Course:
NUC ENG 5509	Nuclear Nonproliferation	3
Elective Courses:
NUC ENG 5207	Nuclear Fuel Cycle	3
NUC ENG 5281	Introduction to Probabilistic Risk Assessment	3
NUC ENG 5312	Nuclear Radiation Measurements and Spectroscopy	3
NUC ENG 5347	Radiological Engineering	3
NUC ENG 5577	Advanced Nuclear Forensics and Radiochemistry	3
NUC ENG 5507	Nuclear Policy	3
NUC ENG 6331	Radiation Shielding	3

Muthanna Hikmat Al Dahhan, Curators' Distinguished Professor
DSc Washington University
Multiphase reaction and reactor engineering flow systems; transport-kinetic integration; advanced measurement and computational techniques; application to green technology and sustainable development in energy, products, and environment.

Ayodeji Babatunde Alajo, Associtate Professor
PHD Texas A&M University
High fidelity nuclear systems design and modeling, criticality safety advanced fuel cycles, radioactive waste management, and nuclear systems safety.

Syed Bahauddin Alam, Assistant Professor
PHD University of Cambridge
Multiscale and Multiple modeling, digital twin, explainable and trustworthy AI, uncertainty quantification, robust optimization.

Carlos Henry Castano Giraldo, Associate Professor
PHD University of Illinois Urbana-Champaign
Energy, nuclear materials, plasma material interactions, hydrogen in materials, radio electromechanical effects and nanotechnology.

Joseph Graham, Associate Professor
PHD University of Texas at Austin
Radiation effects in ceramics, radiation solid interactions, nuclear fuel properties and nuclear waste forms.

Joseph W Newkirk, Professor and Department Chair of Nuclear Engineering and Radiation Science
PHD University of Virginia
Additive manufacturing, powder metallurgy, wear and corrosion resistant alloys, high temperature materials, aerospace materials, nuclear materials, and heat treating.

Joshua P Schlegel, Associate Professor
PHD Purdue University
Two-phase flow experiments and modeling, nuclear reactor thermal hydraulics, heat transfer and fluid mechanics.

Joseph D Smith, Professor and Laufer Endowed Chair in Energy
PHD Brigham Young University
Hybrid energy systems, fuels combustion and gasification, industrial gas flare design, operation and regulation, process modeling, monitoring control and operation.

Shoaib Usman, Associate Professor
PHD University of Cincinnati
Radiation transport, radiation protection, radioactive waste management.

Haiming Wen, Assistant Professor
PHD University of California-Davis