Associate Professor
332-4 Randolph Hall
540-231-9112
540-231-9100- FAX
mark.pierson@vt.edu
| Education | Research | Experience |
Education
Ph.D. |
Mathematics | Virginia Tech | 2005 |
| M.S. | Mathematics | Virginia Tech | 2000 |
| B.A. | German | University of California | 1978 |
Research
- Nuclear Engineering:
- Nuclear safeguards and nonproliferation
- Alternative reactor technology
-Computational methods in reactor physics
-Nuclear fuel cycle
-Reactor operations and safety
- Abstract Differential-Algebraic Equations (DAEs) with application to:
-Navier-Stokes equations
-Computational fluid dynamics
-Applied functional analysis
Teaching Activities
ME 3145-3146 Fundamentals of Nuclear Engineering
Application of fundamental principles of neutron physics and reactor theory. ME 3145: Introduction to nuclear cross-section data, neutron scattering, nuclear fission, and diffusion theory. Examination of current and next generation nuclear power plants. ME 3146: Calculation of critical mass and dimensions of a reactor using modified one-group theory; reactivity changes in the core due to control rods, chemical boron shim, temperature changes, and fission product poisons. Determination of reactor thermal design criteria. Introduction to radiation protection and reactor accident analysis. Nuclear engineering ethical principles.Co-req: Math 2214 for 3145.
ME 4015-4016 Design and Project: Nuclear Engineering Application
This year's project entails design of a functioning circulation pump for a molten salt reactor system. It will require researching alternative pump designs, packing systems, materials selection, and motor requirements to pump a viscous molten salt mixture. In addition, some calculations involving thermal hydraulics will be required to determine the necessary volume flowrate and size of the pump. The goal is to build a working prototype of the pump (using other available materials) by the end of the year. Reports from an actual working molten salt reactor at Oak Ridge National Laboratory in the 1960s will be used as background information and to build upon for a current design. The results of this design effort may end up being used in a future reactor plant design.
ME 4984/5984 Nuclear Fuel Cycle
The uranium nuclear fuel cycle from mining the uranium, to conversion, enrichment, fuel manufacturing, in-core fuel management and refueling, spent fuel storage, reprocessing/recycling and final disposition as waste in a geologic repository.
ME 4974 Independent Study: Nuclear Quality Assurance, Licensing, Standards and Codes
This course will help the student learn the necessary engineering codes and standards applicable to the nuclear industry. This will include nuclear quality assurance, nuclear plant licensing, and detailed technical codes for design and maintenance. Student will be required to meet weekly with the instructor to discuss weekly reading assignments. Written progress reports will be required along with a midterm and final report summarizing relevant codes, standards, and procedures applicable to the nuclear industry and what the student has learned from their review.
Experience
| Nuclear Engineering Research Associate Professor | Dept. of Mechanical Engineering, Virginia Tech Blacksburg, VA |
September 2006 - present |
| Project Manager, Joint Unmanned Systems Test, Experimentation and Research (JOUSTER) | Dept. of Mechanical Engineering Virginia Tech |
Sept. 2005 - Nov. 2007 |
| Proposal Development Manager | Proposal Development Team Research Division Virginia Tech Blacksburg, VA |
Aug 2005 - December 2006 |
| Project Manager | Kimballton Deep Underground Science and Engineering Laboratory (DUSEL) Virginia Tech Blacksburg, VA |
Jun. 2005 - Sept. 2005 |
| Adjunct Professor | Department of Mathematics Virginia Tech |
May 2005 - Present |
| Naval Submarine Officer | United States Navy | 1978 to 2001 |
Honors
Virginia Tech College of Engineering Award for Outreach Excellence, 2008
Phi Kappa Phi, All-disciplines Honor Society
Pi Mu Epsilon, Mathematics Honor Society
Beta Gamma Sigma, Business and Management Honor Society .
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Publications
No publications listed.