ASTM E2006 - 16 Standard Guide for Benchmark Testing of Light Water Reactor Calculations
Citing ASTM Standards Citation data is made available by participants in CrossRefs Cited-by Linking service. A comprehensive list of citations to this standard are listed here.
E482 Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance
E531 Standard Practice for Surveillance Testing of High-Temperature Nuclear Component Materials
E706 Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards
E844 Standard Guide for Sensor Set Design and Irradiation for Reactor Surveillance
E853 Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Neutron Exposure Results
E944 Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance
E1005 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
E1006 Standard Practice for Analysis and Interpretation of Physics Dosimetry Results from Test Reactor Experiments
E2005 Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields
E2956 Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels
Referenced ASTM Standards The documents listed below are referenced within the subject standard but are not provided as part of the standard.
E261 Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
E262 Test Method for Determining Thermal Neutron Reaction Rates and Thermal Neutron Fluence Rates by Radioactivation Techniques
E706 Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards, E 706(0)
E844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E 706 (IIC)
E944 Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, E 706 (IIA)
E1018 Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E706 (IIB)
E2005 Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields