Richard E Hale

Research and Development Staff Member

Richard Hale is a Research and Development Staff Member in the Advanced Reactor Systems and Safety Group, Nuclear Science and Technology Division, Oak Ridge National Laboratory (ORNL), Oak Ridge, TN.

Current work includes systems modeling of small modular nuclear reactors utilizing Modelica based object oriented models, as well as spent fuel systems analysis, and offsite dose consequence  and reactor core steady state heat transfer analysis for the High Flux Isotope Reactor. Finally, recent work towards developing neutron imaging capabilities for advanced thermal performance of electronic thermal ground planes for DARPA is being leveraged towards the development of neutron imaging capabilities for advanced engineering systems across multiple domains.

Recent work included economic analysis of small modular reactors based on International Generation IV baseline models, as well as systems engineering on the TCWS for ITER.  Responsibilities included interface and requirements management using DOORS software as well as system engineering of the cooling water system.

Areas of expertise include atmospheric dispersion and dose consequence analysis, thermal hydraulic analysis, and design basis and severe accident nuclear reactor safety analysis. He has over 25 years of experience in performing nuclear design support and systems analysis for reactor operation, nuclear fuel handling, and spent fuel shipment on a wide range of uniquely designed research reactors at ORNL.

Additional experience includes the following:

  • Performance of analysis in support of unresolved safety question determinations, Safety Analysis Reports (SAR), and Safety Analysis Reports for Packaging (SARP). Richard has performed code development and modification to ORNL thermal hydraulic heat transfer and fluid dynamic analysis codes [HFIR Steady State Heat Transfer Code (SSHTC), HEATING]. 
  • Risk assessment analysis (SAPHIRE) for studies associated with NASA’s Jupiter Icy Moons Orbiter Mission as well as performed safety analysis and served as principle author for several chapters in the High Flux Isotope reactor Safety Analysis Report. 
  • Performed dose consequence analysis in support of an NRC transportation study on a moderator intrusion consequence. In addition, I have performed source term (ORIGEN) and dose consequence and dispersion calculations for the HFIR SAR (NRC Reg Guide 1.145 and 1.4), and for emergency response planning (RASCAL) and NESHAP compliance at ORNL. In this capacity, Richard is familiar with many chemical/radiological accident dose consequence and dispersion codes (CAP88, HOTSPOT, HPAC, ALOHA, MACCS).
  • Serves as a subject matter expert in the ORNL Emergency Operations Center support team, and has served on the ORNL Scientific Computer User’s Advisory Committee.

Mr. Hale holds a B.S. degree in petroleum engineering and M.S. degree in mechanical engineering from the University of Oklahoma.