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    ASTM E2005 - 21

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

    Active Standard ASTM E2005 | Developed by Subcommittee: E10.05

    Book of Standards Volume: 12.02


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    Significance and Use

    3.1 This guide describes approaches for using neutron fields with well known characteristics to perform calibrations of neutron sensors, to intercompare different methods of dosimetry, and to corroborate procedures used to derive neutron field information from measurements of neutron sensor response.

    3.2 This guide discusses only selected standard and reference neutron fields which are appropriate for benchmark testing of light-water reactor dosimetry. The Standard Fields considered here include neutron source environments that closely approximate: a) the unscattered neutron spectra from 252Cf spontaneous fission; and b) the 235U thermal neutron induced fission. These standard fields were chosen for their spectral similarity to the high energy region (E > 2 MeV) of reactor spectra. The various categories of benchmark fields are defined in Terminology E170.

    3.3 There are other well known neutron fields that have been designed to mockup special environments, such as pressure vessel mockups in which it is possible to make dosimetry measurements inside of the steel volume of the “vessel.” When such mockups are suitably characterized, they are also referred to as benchmark fields. A variety of these engineering benchmark fields have been developed, or pressed into service, to improve the accuracy of neutron dosimetry measurement techniques. These special benchmark experiments are discussed in Guide E2006, and in Refs (1)4 and (2).

    1. Scope

    1.1 This guide covers facilities and procedures for benchmarking neutron measurements and calculations. Particular sections of the guide discuss: the use of well-characterized benchmark neutron fields to calibrate integral neutron sensors; the use of certified-neutron-fluence standards to calibrate radiometric counting equipment or to determine interlaboratory measurement consistency; development of special benchmark fields to test neutron transport calculations; use of well-known fission spectra to benchmark spectrum-averaged cross sections; and the use of benchmarked data and calculations to determine the uncertainties in derived neutron dosimetry results.

    1.2 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.

    1.3 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, health, and environmental practices and determine the applicability of regulatory limitations prior to use.

    1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.


    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

    E261 Practice for Determining Neutron Fluence, Fluence Rate, and Spectra 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

    E482 Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance

    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

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

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

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

    E910 Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance

    E1297 Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium

    E2006 Guide for Benchmark Testing of Light Water Reactor Calculations


    ICS Code

    ICS Number Code 27.120.10 (Reactor engineering)

    UNSPSC Code

    UNSPSC Code 26141700(Dosimetry equipment)


    Referencing This Standard
    Link Here
    Link to Active (This link will always route to the current Active version of the standard.)

    DOI: 10.1520/E2005-21

    Citation Format

    ASTM E2005-21, Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields, ASTM International, West Conshohocken, PA, 2021, www.astm.org

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