Reactor and Nuclear Systems Division

Doug Bowen

Doug Bowen

Senior R&D Staff
Nuclear Data and Criticality Safety
Reactor and Nuclear Systems Division
Nuclear Science and Engineering Directorate
Oak Ridge National Laboratory
P.O. Box 2008, Bldg. 5700
Oak Ridge, TN 37831-6170
Phone: 865.576.0315
Fax: 865.576.3513
bowendg@ornl.gov

Curriculum Vitae

 

Research Interests

  • Application of Nuclear criticality safety to operations with fissionable material (process analysis)
  • Nuclear criticality safety calculations
  • Nuclear criticality safety training
  • Nuclear criticality safety accidents

Education

  • Doctoral Candidate, University of New Mexico, Albuquerque, NM (Expected graduation date Summer 2014)
  • M.S., Nuclear Engineering, University of New Mexico, Albuquerque, NM, 1997
  • B.Sc., Nuclear Engineering, University of New Mexico, Albuquerque, NM, 1995

Publications

Bowen, D. G., “The Role of Criticality Safety Officers at Los Alamos National Laboratory,” Los Alamos National Laboratory, LA-UR-09-0606 (2009).

Bowen, D. G., “Integration of NCS in the Chemistry and Metallurgy Research Replacement Facility at Los Alamos National Laboratory,” Los Alamos National Laboratory, LA-UR-09-0607 (2009).

Bowen, D. G. and N. W. Brown, “ANSI/ANS-8.1 Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors,” Los Alamos National Laboratory, LA-UR-08-7219 (2008).

Bowen, D. G. and R. D. Busch, “Hand Calculation Methods for Criticality Safety – A Primer,” LA- 14244-M, Los Alamos National Laboratory (2006).

Bowen, D. G., “ENDF/B Cross-Section Evolution for Criticality Safety Burnup Credit Applications,” Transactions of the American Nuclear Society, 93, 267 (2005).

Bowen, D. G. and R. D. Busch, “Hand Calculational Methods for Criticality Safety – A Primer,” 2005 Nuclear Criticality Safety Division Topical Meeting, Knoxville, TN (2005).

Bowen, D. G., “Preliminary Subcritical Mass and Volume Calculations for Various Plutonium Compounds to Support a Revision to ANSI/ANS-8.1,” Los Alamos National Laboratory, LA-UR-04-7989 (2004).

Bowen, D. G. and R. D. Busch, “Using ORIGEN and MCNP to Calculate Reactor Criticals and Burnup Effects,” Transactions of the American Nuclear Society, 77, 233 (1997).

Bowen, D. G., “The Coupling of ORIGEN and MCNP for Reactor Core and Spent Fuel Criticality Analyses,” Master’s Thesis, University of New Mexico (1997).