Digital Library / Past Symposia for Committee E10 / Reactor Dosimetry, 12th International Symposium

Sponsored by ASTM committee E10 on Nuclear Technology and Applications

May 08 2005 - May 23 2005

• The Validity of the Use of Equivalent DIDO Nickel Dose for Graphite Dosimetry
• TRIM Modeling of Displacement Damage in SiC for Monoenergetic Neutrons
• Characterizing the Time- and Energy-Dependent Reactor n/γ Environment
• Precision Neutron Total Cross-Sectional Measurements for Natural Carbon at Reactor Neutron-Filtered Beams
• Comparison of the Results of the Calculational and Experimental VVER-440 Pressure Vessel Dosimetry at Paks NPP
• Neutron Damage in SiC Semiconductor Radiation Detectors in the GT-MHR
• Measurements and Monte Carlo Calculations of Gamma and Neutron Flux Spectra Inside and Behind Iron/Steel/Water Configurations
• Benchmarking of PENTRAN-SSN Parallel Transport Code and FAST Preconditioning Algorithm Using the VENUS-2 MOX-Fueled Benchmark Problem
• A Beam-Monitor System for Neutrons and Gamma Rays in the Medical Irradiation Facility of the Kyoto University Research Reactor
• Generalized Linear Least-Squares Adjustment, Revisited
• Spallation Radiation Damage Calculations and Database: Cross-Section Discrepancies between the Codes
• Radiation Dosimetry in the BNCT Patient Treatment Room at the Brookhaven Medical Research Reactor
• Characterization of the Neutron Field in the HSSI Reusable Irradiation Facility at the Ford Nuclear Reactor
• Survey of the Latest Evaluated Nuclear Data
• Coarse-Mesh Adjoint Biasing of a Monte Carlo Dose Calculation
• Evaluation of Diamond Detectors for Fast Neutron Fluence Measurements in WWER-1000 Surveillance Assemblies
• A New Derivation of the Perturbation Operator Used in MCNP
• Application of a Silicon Calorimeter in Fast Burst Reactor Environments
• Mesh Tally Radiation Damage Calculations and Application to the SNS Target System
• Neutron Response Function for BC-523A Scintillation Detector in the Energy Range 0.5 MeV to 20 MeV
• Use of CPXSD for Generation of Effective Fast Multigroup Libraries for Pressure Vessel Fluence Calculations
• Digital Multiparameter System for Characterizing the Neutron-Gamma Field in the LR-O Experimental Reactor
• Thermal and Epithermal Fluence Rate Measurements in Multipurpose Reactors: Application of a Least-Squares Fitting Code RESDET to Obtain Thermal and Epithermal Fluence Rates from Measured Reaction Rates
• Retrospective Dosimetry of Fast Neutrons Focused on the Reactions ⁹³Nb(n,n^′)⁹³Nb^m and ⁵⁴Fe(n,p)⁵⁴Mn
• Measurement of Helium Generation in AISI 304 Reflector and Blanket Assemblies after Long-term Irradiation in EBR-II