• ASTM E 393 : 2019

    Current The latest, up-to-date edition.

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

    Available format(s):  Hardcopy, PDF

    Language(s):  English

    Published date:  01-12-2019

    Publisher:  American Society for Testing and Materials

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    1.1This test method describes two procedures for the measurement of reaction rates by determining the amount of the fission product 140Ba produced by the non-threshold reactions 235U(n,f), 241Am(n,f), and 239Pu(n,f), and by the threshold reactions 238U(n,f), 237Np(n,f), and 232Th(n,f).

    1.2These reactions produce many fission products, among which is 140Ba, having a half-life of 12.752 days. 140Ba emits gamma rays of several energies; however, these are not easily detected in the presence of other fission products. Competing activity from other fission products requires that a chemical separation be employed or that the 140Ba activity be determined indirectly by counting its daughter product 140La. This test method describes both procedure (a), the nondestructive determination of 140Ba by the direct counting of 140La several days after irradiation, and procedure (b), the chemical separation of 140Ba and the subsequent counting of 140Ba or its daughter 140 La.

    1.3With suitable techniques, fission neutron fluence rates can be measured in the range from 107 n (neutrons) · cm−2 · s−1 to approximately 1015 n · cm−2 · s−1.

    1.4The measurement of time-integrated reaction rates with fission dosimeters by 140Ba analysis is limited by the half-life of 140Ba to irradiation times up to about six weeks.

    1.5The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.

    1.6This 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.

    1.7This 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.

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    Committee E 10
    Document Type Test Method
    Publisher American Society for Testing and Materials
    Status Current
    Supersedes

    Standards Referencing This Book - (Show below) - (Hide below)

    ASTM E 181 : 2017 Standard Test Methods for Detector Calibration and Analysis of Radionuclides
    ASTM E 1018 : 2009 : R2013 : EDT 1 Standard Guide for Application of ASTM Evaluated Cross Section Data File
    ASTM E 170 : 2020 Standard Terminology Relating to Radiation Measurements and Dosimetry
    ASTM E 181 : 2023 Standard Guide for Detector Calibration and Analysis of Radionuclides in Radiation Metrology for Reactor Dosimetry
    ASTM E 944 : 1996 Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, (IIA)
    ASTM E 261 : 2016 Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
    ASTM E 170 : 2023 Standard Terminology Relating to Radiation Measurements and Dosimetry
    ASTM E 1005 : 2021 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
    ASTM E 704 : 1996 Standard Test Method for Measuring Reaction Rates by Radioactivation of Uranium-238
    ASTM E 1018 : 2020 : EDT 1 Standard Guide for Application of ASTM Evaluated Cross Section Data File
    ASTM E 705 : 1996 Standard Test Method for Measuring Reaction Rates by Radioactivation of Neptunium-237
    ASTM E 261 : 2016 : R2021 Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
    ASTM E 1005 : 2016 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
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