Douglas G Bowen Section Head, Nuclear Data, Criticality Safety, and Radiation Transport Contact 865.576.0315 | BOWENDG@ORNL.GOV All Publications Calculation of Extended Subcritical Mass Limits in ANSI/ANS-8.1-2014... An Approach to Obtaining the Best-Estimate keff for Uncertainty in ZPPR Plates USE OF SCALE MAVRIC RADIATION TRANSPORT CALCULATIONS FOR THE DESIGN OF A SUBCRITICAL ASSEMBLY AT OAK RIDGE NATIONAL LABORATORY ANS-8 Nuclear Criticality Safety Standards -- Are they Risk Informed, Performance Based?... ANS-8 Nuclear Criticality Safety Consensus Standards -- Current Initiatives... OVERVIEW AND CURRENT PROGRESS OF THE DOE/NNSA NUCLEAR CRITICALITY SAFETY PROGRAM TRAINING AND EDUCATION PROGRAM BASIS OF 10CFR71.15(B) FOR CONSIDERATION INTO SSR-6 PARA. 417 Nuclear Criticality Safety Training: Needs and Efforts BASIS FOR FISSILE EXEMPTION 10CFR71.15(B) Conduct of Operations and Nuclear Criticality Safety Standards Hand Calculation Methods for Nuclear Criticality Safety Volume 9: Critical Facility with Add-On Ion Beam Proposed Subcritical Assembly for Nuclear Criticality Safety Training at the 91°µÍø Current Progress of the Final Design of a Subcritical Assembly at the 91°µÍø... DOE-EM NCS Needs Program History and Current Efforts Update of the Nuclear Criticality Slide Rule: Review of the Estimation of the Number of Fissions... Update of the Nuclear Criticality Slide Rule Calculations: Plutonium systems – Delayed Fission Gamma Domestic and International Standards for Nuclear Criticality Safety -- Overview and Status CURRENT STATUS OF THE DOE/NNSA NUCLEAR CRITICALITY SAFETY PROGRAM HANDS-ON CRITICALITY SAFETY TRAINING COURSES A Subcritical Assembly for Training and Education Use at the 91°µÍø HAND CALCULATIONS FOR NUCLEAR CRITICALITY SAFETY – PRIMER REVISION Update of the Nuclear Criticality Slide Rule Calculations: Plutonium Systems – Delayed Fission Gamma Continuous-Energy ENDF/B-VIII.0 Cross Section and SCALE 6.2.4 Performance for Nuclear Criticality Safety Applications: 1H, C, 58,60Ni, 182,183,184,186W, 235,238U, 239Pu Criticality Accident Alarm System Shielding Benchmark: Integral Experiment Request 498, Critical Engineering Decision 2 Report Comparison of ISO and ANSI/ANS Nuclear Criticality Safety Standards Pagination Current page 1 Page 2 Page 3 Next page ›â¶Äº Last page Last » Key Links Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Data, Criticality Safety, and Radiation Transport Section SCALE