ASTM E1006-96 - 1.1.1996
 
1. Scope

1.1 This practice covers the methodology summarized in Annex A 1 to be used in the analysis and interpretation of physics-dosimetry results from test reactors.

1.2 This practice relies on, and ties together, the application of several supporting ASTM standard practices, guides, and methods that are in various stages of completion (see Matrix E 706).

1.3 Support subject areas that are discussed include reactor physics calculations, dosimeter selection and analysis, exposure units, and neutron spectrum adjustment methods.

1.4 This practice is directed towards the development and application of physics-dosimetry-metallurgical data obtained from test reactor irradiation experiments that are performed in support of the operation, licensing, and regulation of LWR nuclear power plants. It specifically addresses the physics-dosimetry aspects of the problem. Procedures related to the analysis, interpretation, and application of both test and power reactor physics-dosimetry-metallurgy results are addressed in Practices E 185, E 560, E 853, and E 1035, Matrix E 706(IE), Guide E 900, and Test Method E 646.

1.5 This standard may involve hazardous materials, operations, and equipment. This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

 
2. Referenced Documents

E693-23

Standard Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA)

E1018-20e1

Standard Guide for Application of ASTM Evaluated Cross Section Data File (Includes all amendments and changes 7/2/2020).

E646-16(2024)

Standard Test Method for Tensile Strain-Hardening Exponents (n -Values) of Metallic Sheet Materials

E482-22

Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance

E900-21e1

Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials (Includes all amendments and changes 11/26/2025).

E2006-22

Standard Guide for Benchmark Testing of Light Water Reactor Calculations

E910-24

Standard Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance

E854-19

Standard Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance

E853-25

Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Neutron Exposure Results

E944-26

Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance

E1005-21

Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance

E706-23

Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards

E844-25

Standard Guide for Sensor Set Design and Irradiation for Reactor Surveillance

E2005-21

Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields

E1035-18(2023)

Standard Practice for Determining Neutron Exposures for Nuclear Reactor Vessel Support Structures

E185-25

Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels