References
- T. COUSINS, T. JONES, J. R. BRISSON, J. E. MCFEE T. J. JAMIESON, E. J. WALLER, F. J. LEMAY, H. ING, C. E. CLIFFORD, and B. SELKIRK, “The Development of a Thermal Neutron Activation (TNA) System as a Confirmatory Non-Metallic Land Mine Detector,” J. Radioanal. Nucl. Chem., 235, 1–2, 53 (1998).
- M. LUSZIK-BHADRA, T. BOLOGNESE-MILSZTAJN, M. BOSCHUNG, M. COECK, D. DERDAU, F. d’ERRICO, A. FIECHTNER, J. KYLLONEN, V. LACOSTE, B. LIEVENS, and L. LINDBORG, “Summary of Personal Neutron Dosemeter Results ObtainedWithin the EVIDOS Project,” Radiat. Prot. Dosim., 125, 293 (2007).
- D. STODDARD and H. HOOTMAN “Cf-252 Shielding Guide,” DP-1246, Savannah River Laboratory (1971).
- H. ING, T. CLIFFORD, T. MCLEAN, W. WEBB, T. COUSINS, and J. DHERMAIN, “ROSPEC—ASimple Reliable High Resolution Neutron Spectrometer,” Radiat. Prot. Dosim., 70, 273 (1997).
- T. COUSINS and T. JONES, “DRDC Ottawa Report on DSSPM Tasking A84867JJ11,” Technical Note, Defence Research and Development Canada–Ottawa (2007).
- “Operational Characteristics Technical Specifications and Evaluation Criteria for RADIAC Equipment for Use Under Low Level Radiation Conditions,” Addendum to NATO Document AC/255 (Panel VII) D0104.
- “MCNPX ExtensionsVersion 2.6.b,” LA-UR-06-3248, Los Alamos National Laboratory (2006).
- “MCNPDATA: Standard Neutron, Photoatomic, Photonuclear, and Electron Data Libraries for MCNP and MCNPX,” LA-CC-02-083, Los Alamos National Laboratory (2005).
- “Neutron Dosimetry for Biology and Medicine,” International Commission on Radiation Units and Measurements, ICRU Report 26, Washington, D.C. (1977).
- “ICRP Publication 74: Conversion Coefficients for Use in Radiological Protection Against External Radiation,” International Commission on Radiological Protection (1996).
- K. VAN RIPER, “SABRINA User’s Guide, Windows Version,” White Rock Science (2001).
- K. ECKERMAN, “The ORNL Mathematical Phantom Series”; http://ordose.ornl.gov/resources/phantom.html.
- K. VAN RIPER, “BODYBUILDER User’s Guide, Windows Version,” White Rock Science (2001).
- “MCNP—A General Monte Carlo N-Particle Transport Code, Version 4B,” LA-12625-M, J. BRIESMEISTER, Ed., Los Alamos National Laboratory (1997).
- “Data for Protection Against Ionizing from External Sources—Supplement to ICRP Publication 15,” ICRP Publication 21, International Commission on Radiological Protection.
- “Protection Against Neutron Radiation,” NCRP Report 38, National Council on Radiation Protection and Measurements.
- L. UNGER and D. TRUBEY, “Specific Gamma-Ray Dose Constants for Nuclides Important to Dosimetry and Radiological Assessment,” ORNL/RSIC-45/R1, Oak Ridge National Laboratory (1982).
- C. WRIGHT, “Radiation Protection for Safe Handling of 252Cf Sources,” DP-MS-68-51, Savannah River Laboratory (1968).
- T. BOLOGNESE-MILSZTAJN, M. GINJAUME, M. MUSZIK-BHADRA, F. VANHAVERE, W. WAHL, and A. WEEKS, “Active Personal Dosemeters for Individual Monitoring and Other New Developments,” Radiat. Prot. Dosim., 112, 1, 141 (2004).
- L. ERHARDT, L. PRUD’HOMME-LALONDE, T. COUSINS, D. ESTAN, and B. HORVATH, “Comparison of Radiation Response of LiF:MgCuP and Al2O3:C Thermoluminescent Dosimeters,” DREO TM 2001-074, Technical Memorandum, Defence Research Establishment Ottawa (2001).