ASTM E261 - 10

    Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques

    Active Standard ASTM E261 | Developed by Subcommittee: E10.05

    Book of Standards Volume: 12.02


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    Significance and Use

    Transmutation ProcessesThe effect on materials of bombardment by neutrons depends on the energy of the neutrons; therefore, it is important that the energy distribution of the neutron fluence, as well as the total fluence, be determined.

    1. Scope

    1.1 This practice describes procedures for the determination of neutron fluence rate, fluence, and energy spectra from the radioactivity that is induced in a detector specimen.

    1.2 The practice is directed toward the determination of these quantities in connection with radiation effects on materials.

    1.3 For application of these techniques to reactor vessel surveillance, see also Test Methods E1005.

    1.4 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.

    Note 1—Detailed methods for individual detectors are given in the following ASTM test methods: E262, E263, E264, E265, E266, E343, E393, E481, E523, E526, E704, E705, and E854.


    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

    E170 Terminology Relating to Radiation Measurements and Dosimetry

    E181 Test Methods for Detector Calibration and Analysis of Radionuclides

    E262 Test Method for Determining Thermal Neutron Reaction Rates and Thermal Neutron Fluence Rates by Radioactivation Techniques

    E263 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Iron

    E264 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Nickel

    E265 Test Method for Measuring Reaction Rates and Fast-Neutron Fluences by Radioactivation of Sulfur-32

    E266 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Aluminum

    E343 Test Method for Measuring Reaction Rates by Analysis of Molybdenum-99 Radioactivity From Fission Dosimeters

    E393 Test Method for Measuring Reaction Rates by Analysis of Barium-140 From Fission Dosimeters

    E481 Test Method for Measuring Neutron Fluence Rates by Radioactivation of Cobalt and Silver

    E523 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Copper

    E526 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Titanium

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

    E704 Test Method for Measuring Reaction Rates by Radioactivation of Uranium-238

    E705 Test Method for Measuring Reaction Rates by Radioactivation of Neptunium-237

    E722 Practice for Characterizing Neutron Fluence Spectra in Terms of an Equivalent Monoenergetic Neutron Fluence for Radiation-Hardness Testing of Electronics

    E844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E 706 (IIC)

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

    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)

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

    ISO Standard

    GuideintheExpression


    ICS Code

    ICS Number Code 17.240 (Radiation measurements); 27.120.30 (Fissile materials and nuclear fuel technology)

    UNSPSC Code

    UNSPSC Code 26141700(Dosimetry equipment)


    DOI: 10.1520/E0261-10

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