Edward Blandford

Contact


Phone: (505)-277-7964
Fax: (505) 277-5433

Physical Address

Room 418
Mechanical Engineering

Photo: true

Assistant Professor

Department of Nuclear Engineering

Personal Website

Education

Ph.D. University of California, Berkeley, Nuclear Engineering, 2010

M.S. University of California, Berkeley, Nuclear Engineering, 2008

B.S. University of California, Los Angeles, Mechanical Engineering, 2002

Biography

Dr. Blandford joined the University of New Mexico as an assistant professor in the Fall of 2012. Prior to that, Dr. Blandford was a Stanton Nuclear Security Fellow at the Center for International Security and Cooperation at Stanford University where he worked dominantly on reactor safety issues and safeguards technology development for pyroprocessing technology. He also worked for several years as a project manager at the Electric Power Research Institute focusing on steam generator thermal-hydraulics and material degradation management. Dr. Blandford’s research interests at UNM include risk-informed design guidance for advanced reactors including reliability of passive safety systems, thermal-fluids experimental validation, fluoride salt-cooled high temperature reactor technology development, LWR severe accident experimentation, and process monitoring simulation for safeguards applications.

Professional Experience

  • 2012-present • University of New Mexico • Assistant Professor • Nuclear Engineering Department
  • 2011-2012 • University of New Mexico • Adjunct Research Assistant Professor • Chemical and Nuclear Engineering Department
  • 2011-2012 • Stanford University • Stanton Nuclear Security Fellow
  • 2010-2011 • Stanford University • Postdoctoral Fellow, CISAC
  • 2003-2006 • Electric Power Research Institute, Palo Alto, California • Project Manager, Steam Generator Management Program
  • 2002-2003 • Electric Power Research Institute, Palo Alto, California • Member of the Technical Staff, Fuel Reliability Program

Publications

  • A. Ali, D. LaBrier, E. D. Blandford and K. Howe, “Corrosion and Solubility in a TSP-Buffered Chemical Environment following a Loss of Coolant Accident: Part 4 – Integrated Chemistry Modeling,” Nuclear Engineering and Design 300 (2016) 644-654.
  • S. Olson, A. Ali, D. LaBrier, E. D. Blandford and K. Howe, “Corrosion and Solubility in a TSP-Buffered Chemical Environment following a Loss of Coolant Accident: Part 3 - Calcium,” Nuclear Engineering and Design 300 (2016) 632–643.
  • A. F. Ali and E. D. Blandford, “An Experimental Study on Head Loss of Prototypical Fibrous Debris Beds During Loss of Coolant Accident”, ASME Journal of Nuclear Engineering and Radiation Science, (Accepted for publication)
  • D. Pease, D. LaBrier, A. Ali, E. D. Blandford and K. Howe, “Corrosion and Solubility in a TSP-Buffered Chemical Environment following a Loss of Coolant Accident: Part 2 - Zinc,” Nuclear Engineering and Design 300 (2016) 620–631.
  • K. Howe, L. Mitchell, S. J. Kim, E. D. Blandford and E. J. Kee, “Corrosion and Solubility in a TSP-Buffered Chemical Environment following a Loss of Coolant Accident: Part 1 - Aluminum,” Nuclear Engineering and Design 282 (2015) 296–305.
  • S.J. Kim, J. Leavitt, K. Hammond, L. Mitchell, E. Kee, K. Howe, and E. D. Blandford, “An Experimental Study of the Corrosion and Precipitation of Aluminum in the Presence of Tri-Sodium Phosphate Buffer Following a Loss of Coolant Accident (LOCA) Scenario,” Nuclear Engineering and Design 282 (2015) 71–82.
  • P.L. Lafreniere, D. Rappleye, R. Hoover, M. Simpson, and E. D. Blandford, "Application of Signature-Based Safeguards to Electrorefining and the Ingot Casting Process," Nuclear Technology 189 (2015) 1-13
  • R. O. Scarlat, M. R. Laufer, E. D. Blandford, N. Zweibaum, D. Krumwiede, A. T. Cisneros, C. Andreades, C. W. Forsberg, E. Greenspan, L. W. Hu, and P. F. Peterson, “Design and licensing strategies for the fluoride-salt-cooled, high-temperature reactor (FHR) technology, “Progress in Nuclear Energy 77 (2014) 406–420.
  • E. D. Blandford and P. F. Peterson, “A Buoyantly-driven Shutdown Rod Concept for Passive Reactivity Control of Liquid-Salt Cooled High Temperature Reactor”, Nuclear Engineering and Design 262 (2013) 600-610   

Teaching Interests

  • Introductory reactor physics
  • Radioactive waste management
  • Reactor safety

Research Interests

  • Nuclear reactor thermal-fluids in support of the safety of nuclear installations
  • Liquid fluoride salt reactor design
  • Best-estimate code validation
  • Risk-informed design guidance for advanced reactor systems and back-end separation facilities
  • Physical protection strategies and risk management

Center/Laboratory/Program Affiliations