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Digital Library/Symposia/E10/Reactor Dosimetry, 12th Volume
Sponsored by ASTM committee E10 on Nuclear Technology and Applications
May 08 2005 - May 13 2005
Papers Published from this Symposium
Calculation of Neutron Fluxes for Radioactive Inventory Assessment of Magnox Power Plant
Attenuation of Radiation Damage and Neutron Field in Reactor Pressure Vessel Wall
Reactor Dosimetry Issues During Justification of Extension of Service Life of Nonrestorable Equipment of Russian VVER
Retrospective Measurement of Neutron Activation within the Pressure Circuit Steelwork of a Magnox Reactor and Comparison with Prediction
The Neutron Spectrum of NBS-1
Sensitivity Analysis and Neutron Fluence Adjustment for VVER-440 RPV
An International Evaluation of the Neutron Cross Section Standards
Extensive Revision of the Kernel-based PREVIEW Program and Its Input Data
Spent Fuel Monitoring with Silicon Carbide Semiconductor Neutron/Gamma Detectors
Verification of MultiTrans Calculations by the VENUS-3 Benchmark Experiment
Neutron and Photon Dosimetry at the LR-0 Reactor Using Paired Detectors
Determination of Adjusted Neutron Spectra in Different MUSE Configurations by Unfolding Techniques
Fast Neutron Dosimetry and Spectrometry Using Silicon Carbide Semiconductor Detectors
Benchmark on the 3-D VENUS-2 MOX-Fueled Reactor Dosimetry Calculations by DANTSYS Code System
Dosimetry Requirements for Pressure Vessel Steels Toughness Curve in the Ductile to Brittle Range
Advances in Calculation of Fluence to Reactor Structures
Experimental and Calculation Investigations of the Space-Energy Neutron and Photon Distribution in the Vicinity of Reactor Pressure Vessel and Surveillance Specimen Box of New Type in the WWER-1000 Mock-Up
Comparison of Predicted and Measured Helium Production in U.S. BWR Reactors
Validation of the Neutron Fluence Calculation on the VVER-440 RPV Support Structure
Reactor Dosimetry with Niobium
Gas Production in Reactor Materials
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