ASTM E1006-13
Standard Practice for Analysis and Interpretation of Physics Dosimetry Results from Test Reactor Experiments

Standard No.

ASTM E1006-13

Release Date

2013

Published By

American Society for Testing and Materials (ASTM)

Status

Be replaced

Replace By

ASTM E1006-21

Latest

ASTM E1006-21

Scope

3.1 The mechanical properties of steels and other metals are altered by exposure to neutron radiation. These property changes are assumed to be a function of chemical composition, metallurgical condition, temperature, fluence (perhaps also fluence rate), and neutron spectrum. The influence of these variables is not completely understood. The functional dependency between property changes and neutron radiation is summarized in the form of damage exposure parameters that are weighted integrals over the neutron fluence spectrum.

3.2 The evaluation of neutron radiation effects on pressure vessel steels and the determination of safety limits require the knowlege of uncertainties in the prediction of radiation exposure parameters (for example, dpa (Practice E693), neutron fluence greater than 1.0 MeV, neutron fluence greater than 0.1 MeV, thermal neutron fluence, etc.). This practice describes recommended procedures and data for determining these exposure parameters (and the associated uncertainties) for test reactor experiments.

3.3 The nuclear industry draws much of its information from databases that come from test reactor experiments. Therefore, it is essential that reliable databases are obtained from test reactors to assess safety issues in Light Water Reactor (LWR) nuclear power plants.

1.1 This practice covers the methodology summarized in Annex A1 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.

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 E185, E853, and E1035, Guides E900, E2005, E2006 and Test Method E646.

1.5 This standard may involve hazardous mate......

ASTM E1006-13 Referenced Document

• ASTM E1005 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706(IIIA)
• ASTM E1018 Standard Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E 706 (IIB)
• ASTM E1035 Standard Practice for Determining Radiation Exposures for Nuclear Reactor Vessel Support Structures
• ASTM E185 Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, E706 (IF)
• ASTM E2005 Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields
• ASTM E2006 Standard Guide for Benchmark Testing of Light Water Reactor Calculations
• ASTM E482 Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)
• ASTM E646 Standard Test Method for Tensile Strain-Hardening Exponents (n -Values) of Metallic Sheet Materials*， 2024-04-20 Update
• ASTM E693 Standard Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA), E706(ID)
• ASTM E706 Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards, E706(0)
• ASTM E844 Standard Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E 706(IIC)
• ASTM E853 Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Results, E706(IA)
• ASTM E854 Standard Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance, E706(IIIB)
• ASTM E900 Standard Guide for Predicting Neutron Radiation Damage to Reactor Vessel Materials, E 706 (IIF)
• ASTM E910 Standard Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance, E706 (IIIC)
• ASTM E944 Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, (IIA)

ASTM E1006-13 history

• 2021 ASTM E1006-21 Standard Practice for Analysis and Interpretation of Physics Dosimetry Results from Test Reactor Experiments
• 2013 ASTM E1006-13 Standard Practice for Analysis and Interpretation of Physics Dosimetry Results from Test Reactor Experiments
• 2008 ASTM E1006-08 Standard Practice for Analysis and Interpretation of Physics Dosimetry Results for Test Reactors, E 706(II)
• 2002 ASTM E1006-02 Standard Practice for Analysis and Interpretation of Physics Dosimetry Results for Test Reactors, E 706(II)
• 1996 ASTM E1006-96 Standard Practice for Analysis and Interpretation of Physics Dosimetry Results for Test Reactors, E 706(II)