ASTM E 481 : 2023
Current
The latest, up-to-date edition.
Standard Practice for Measuring Neutron Fluence Rates by Radioactivation of Cobalt and Silver
Hardcopy , PDF
English
07-17-2023
Committee |
E 10
|
DocumentType |
Standard Practice
|
Pages |
7
|
PublisherName |
American Society for Testing and Materials
|
Status |
Current
|
Supersedes |
1.1This practice covers a suitable means of obtaining the thermal neutron fluence rate, or fluence, in nuclear reactor environments where the use of cadmium, as a thermal neutron shield as described in Test Method E262, is undesirable for reasons such as potential spectrum perturbations or due to temperatures above the melting point of cadmium.
1.2The reaction 59Co(n,γ )60Co results in a well-defined gamma emitter having a half-life of 5.2711 years2 (8)3 (1).4 The reaction 109Ag(n,γ)110mAg results in a nuclide with a well-known, complex decay scheme with a half-life of 249.78 (2) days (1). Both cobalt and silver are available either in very pure form or alloyed with other metals such as aluminum. A reference source of cobalt in aluminum alloy to serve as a neutron fluence rate monitor wire standard is available from the National Institute of Standards and Technology (NIST) as Standard Reference Material (SRM) 953.5 The competing activities from neutron activation of other isotopes are eliminated, for the most part, by waiting for the short-lived products to die out before counting. With suitable techniques, thermal neutron fluence rate in the range from 108 cm−2·s−1 to 3 × 1015 cm−2·s−1 can be measured. Two calculational practices are described in Section 9 for the determination of neutron fluence rates. The practice described in 9.3 may be used in all cases. This practice describes a means of measuring a Westcott neutron fluence rate in 9.2 (Note 1) by activation of cobalt- and silver-foil monitors (see Terminology E170). For the Wescott Neutron Fluence Convention method to be applicable, the measurement location must be well moderated and be well represented by a Maxwellian low-energy distribution and an (1/E) epithermal distribution. These conditions are usually only met in positions surrounded by hydrogenous moderator without nearby strongly multiplying or absorbing materials.
Note 1:Westcott fluence rate
1.3The values stated in SI units are to be regarded as the standard, except in the case of nuclear data where the source referenced units are retained in order to preserve the integrity of the referenced uncertainty values.
1.4This 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.
1.5This 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.
ASTM E 944 : 2019 | Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance |
ASTM E 262 : 2017 | Standard Test Method for Determining Thermal Neutron Reaction Rates and Thermal Neutron Fluence Rates by Radioactivation Techniques |
ASTM E 1005 : 2021 | Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance |
ASTM E 1854 : 2019 | Standard Practice for Ensuring Test Consistency in Neutron-Induced Displacement Damage of Electronic Parts |
ASTM E 261 : 2016 : R2021 | Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques |
ASTM E 262 : 2017 : R2024 : EDT 1 | Standard Test Method for Determining Thermal Neutron Reaction Rates and Thermal Neutron Fluence Rates by Radioactivation Techniques |
ASTM E 170 : 2024 | Standard Terminology Relating to Radiation Measurements and Dosimetry |
ASTM E 170 : 2023 | Standard Terminology Relating to Radiation Measurements and Dosimetry |
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