ASTM E1006 - 13

    Standard Practice for Analysis and Interpretation of Physics Dosimetry Results from Test Reactor Experiments

    Active Standard ASTM E1006 | Developed by Subcommittee: E10.05

    Book of Standards Volume: 12.02


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    Significance and Use

    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. Scope

    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 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 (purchase separately) The documents listed below are referenced within the subject standard but are not provided as part of the standard.

    ASTM Standards

    E185 Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels

    E482 Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)

    E646 Test Method for Tensile Strain-Hardening Exponents (n -Values) of Metallic Sheet Materials

    E693 Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA), E 706(ID)

    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)

    E853 Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Results

    E854 Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance, E706(IIIB)

    E900 Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials, E706 (IIF)

    E910 Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance, E706 (IIIC)

    E944 Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, E 706 (IIA)

    E1005 Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706 (IIIA)

    E1018 Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E706 (IIB)

    E1035 Practice for Determining Neutron Exposures for Nuclear Reactor Vessel Support Structures

    E2005 Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields

    E2006 Guide for Benchmark Testing of Light Water Reactor Calculations


    ICS Code

    ICS Number Code 17.240 (Radiation measurements)

    UNSPSC Code

    UNSPSC Code 46171638(Radiation detector and alarm); 26141700(Dosimetry equipment)


    DOI: 10.1520/E1006

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