All Stories

  1. RAMSES impact on Sandia's pulsed power program
  2. Qualitative Conditions for Reasonable Estimates of Kerma Using Total and Kerma Cross Section Attenuation of Photons
  3. Use of Kerma for Subzone Dimension Specification in Monte Carlo Based Photon Energy Deposition Calculations
  4. Integrated Tiger Series (ITS) Code Validation and Uncertainty Quantification for Electron Number Albedo in Various Materials
  5. ITS Version 6.7: The Integrated TIGER Series of Coupled Electron/Photon Monte Carlo Transport Codes User's Manual
  6. Updates to SNL Nuclear Criticality Safety Benchmark Suite for MCNP
  7. Time- and Energy-Resolved Coupled Saturn Radiation Environments Simulations Using the Integrated Tiger Series (ITS) Code
  8. An X-ray Intensity Operations Monitor (AXIOM) (Final LDRD Project Report)
  9. Saturn Radiation Dose Environment Characterization
  10. Simulation and Modeling of Time-Resolved X-Ray Detector for the Saturn Accelerator
  11. Radiation Transport Simulation of the Sulfur Counting System in the Radiation Metrology Laboratory (RML)
  12. Historical Examination of the ASTM Standard E722 1-MeV Silicon Equivalent Fluence Metric
  13. Low Energy Photon Filter Box Optimization Study for the Gamma Irradiation Facility (GIF)
  14. Co-60 Filter Box Optimization
  15. Average X-Ray Energy from Optimized Tantalum / Carbon Bremsstrahlung Converters
  16. Silicon Damage Response Function Derivation and Verification: Assessment of Impact on ASTM Standard E722
  17. Characterization of the Annular Core Research Reactor (ACRR) Neutron Radiography System Imaging Plane
  18. Modeling, Calibration, and Verification of a Fission Chamber for ACRR Experimenters
  19. Development of a Neutron Spectroscopic System Utilizing Compressed Sensing Measurements
  20. Creation of a Benchmark Suite for SNL Nuclear Criticality Safety Code Validation (Volume 1 - MCNP)
  21. A software tool to create material descriptions for neutron transport calculations
  22. Impact of ASTM Standard E722 update on radiation damage metrics
  23. Reactor Pulse-Repeatability Studies at the Annular Core Research Reactor
  24. Reactor Pulse-Repeatability Studies at the Annular Core Research Reactor
  25. Reactor Pulse-Repeatability Studies at the Annular Core Research Reactor
  26. CHARACTERIZATION OF NEUTRON TEST FACILITIES AT SANDIA NATIONAL LABORATORIES
  27. CONTROL ROD REACTIVITY CURVES FOR THE ANNULAR CORE RESEARCH REACTOR
  28. Determination of late-time Gamma-Ray (60Co) sensitivity of single diffusion Lot 2N2222A transistors.
  29. Simultaneous Evaluation of Neutron Spectra and 1-MeV-Equivalent (Si) Fluences at SPR-III and ACRR
  30. Application of a Silicon Calorimeter in Fast Burst Reactor Environments
  31. MCNP/MCNPX model of the annular core research reactor.
  32. Experiment summary for n/y attenuation through materials (Environments 1A).
  33. Benchmark Experiments/Calculations of Neutron Environments in the Annular Core Research Reactor
  34. Diamond PCD for Reactor active dosimetry applications
  35. Neutron contribution to CaF/sub 2/:Mn thermoluminescent dosimeter response in mixed (n//spl gamma/) field environments
  36. CHARACTERIZATION OF ACRR REFERENCE BENCHMARK FIELD
  37. Neutron Contribution to CaF2:Mn Thermoluminescent Dosimeter Response in Mixed (n/y) Field Environments
  38. Benchmark Experiments/Calculations of Neutron Environments in the Annular Core Research Reactor
  39. Development of a Silicon Calorimeter for Dosimetry Applications in a Water-Moderated Reactor
  40. Application of a Silicon Calorimeter in Fast Burst Reactor Environments