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ASTM E 523 : 2016 : REDLINE

Superseded

Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

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

Available format(s)

PDF

Superseded date

28-04-2021

Language(s)

English

Published date

01-12-2016

€59.22
Excluding VAT

CONTAINED IN VOL. 12.02, 2017 Defines procedures for measuring reaction rates by the activation reaction [63]Cu(n,alpha)[60]Co.

Committee
E 10
DocumentType
Redline
Pages
5
PublisherName
American Society for Testing and Materials
Status
Superseded
SupersededBy

1.1This test method covers procedures for measuring reaction rates by the activation reaction 63Cu(n,α) 60Co. The cross section for 60Co produced in this reaction increases rapidly with neutrons having energies greater than about 4.5 MeV. 60Co decays with a half-life of 1925.27 days (±0.29 days)(1)2 and emits two gamma rays having energies of 1.1732278 and 1.332492 MeV(1). The isotopic content of natural copper is 69.17 % 63Cu and 30.83 % 65Cu(2). The neutron reaction, 63Cu(n,γ)64Cu, produces a radioactive product that emits gamma rays (1.34577 MeV (E1005)) which might interfere with the counting of the 60Co gamma rays.

1.2With suitable techniques, fission-neutron fluence rates above 109 cm−2·s−1 can be determined. The 63Cu(n,α)60Co reaction can be used to determine fast-neutron fluences for irradiation times up to about 15 years, provided that the analysis methods described in Practice E261 are followed. If dosimeters are analyzed after irradiation periods longer than 15 years, the information inferred about the fluence during irradiation periods more than 15 years before the end of the irradiation should not be relied upon without supporting data from dosimeters withdrawn earlier.

1.3Detailed procedures for other fast-neutron detectors are referenced in Practice E261.

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

ASTM E 2005:2010 Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields
ASTM E 2005 : 2010 : R2015 Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields
ISO 19226:2017 Nuclear energy — Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals
ASTM E 1005 : 2016 : REDLINE Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
BS ISO 19226:2017 Nuclear energy. Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals
ASTM E 261 : 2016 : REDLINE Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
ASTM E 721 : 2016 : REDLINE Standard Guide for Determining Neutron Energy Spectra from Neutron Sensors for Radiation-Hardness Testing of Electronics
ASTM E 944 : 2013-01 GUIDE FOR APPLICATION OF NEUTRON SPECTRUM ADJUSTMENT METHODS IN REACTOR SURVEILLANCE
17/30337935 DC : 0 BS ISO 19226 - NUCLEAR ENERGY - DETERMINATION OF NEUTRON FLUENCE AND DISPLACEMENTS PER ATOM (DPA) IN REACTOR VESSEL AND INTERNALS
ASTM B 447 : 2012 : REV A : REDLINE Standard Specification for Welded Copper Tube
ASTM E 1854 : 2013 : REDLINE Standard Practice for Ensuring Test Consistency in Neutron-Induced Displacement Damage of Electronic Parts

ASTM E 181 : 2017 : REDLINE Standard Test Methods for Detector Calibration and Analysis of Radionuclides
ASTM E 170 : 2017 : REDLINE Standard Terminology Relating to Radiation Measurements and Dosimetry
ASTM E 1005 : 2016 : REDLINE Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
ASTM E 261 : 2016 : REDLINE Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
ASTM E 944 : 2013-01 GUIDE FOR APPLICATION OF NEUTRON SPECTRUM ADJUSTMENT METHODS IN REACTOR SURVEILLANCE

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