ASTM E523

Refer to Guide E 844 for the selection, irradiation, and quality control of neutron dosimeters.

Refer to Practice E 261 for a general discussion of the measurement of fast neutron fluence rate with threshold detectors. The general shape of the ⁶³Cu(n,α)⁶⁰Co cross section is also shown in Fig. 1(3). This figure is for illustrative purposes only to indicate the range of response of the ⁶³Cu(n,α) reaction. Refer to Guide E 1018 for descriptions of recommended tabulated dosimetry cross sections.

Note 1—The cross section appropriate for use under this standard is ENBDF/B-VI release 8 library since it contains a covariance matrix. The ENDF/B-VII library has been released, but it does not contain a covariance matrix for this reaction. For dosimetry applications, an uncertainty metric expressed as a covariance matrix is required. See Guide E 1018.

The chief advantages of copper for measuring fast-neutron fluence rate are that it has good strength, is easily fabricated, has excellent corrosion resistance, has a melting temperature of 1083°C, and can be obtained pure. The half-life of ⁶⁰Co is long and its decay scheme is simple and well known.

The disadvantages of copper for measuring fast neutron fluence rate are the high reaction apparent threshold of 5 MeV, the possible interference from cobalt impurity (>1 μg/g), the reported possible thermal component of the (n,α) reaction, and the possibly significant cross sections for thermal neutrons for ⁶³Cu and ⁶⁰Co (that is 4.5 and 2.0 barns, respectively),(4) which will require burnout corrections at high fluences.

FIG. 1 ⁶³Cu(n,α)⁶⁰Co Cross Section

1. Scope

1.1 This test method covers procedures for measuring reaction rates by the activation reaction ⁶³Cu(n,)⁶⁰Co. The cross section for ⁶⁰Co produced in this reaction increases rapidly with neutrons having energies greater than about 5 MeV. ⁶⁰Co decays with a half-life of 1925.28 days (0.5 days)() and emits two gamma rays having energies of 1.1732228 and 1.332492 MeV (). The isotopic content of natural copper is 69.17 % ⁶³Cu and 30.83 % ⁶⁵Cu(). The neutron reaction, ⁶³Cu(n,)⁶⁴Cu, produces a radioactive product that emits gamma rays which might interfere with the counting of the ⁶⁰Co gamma rays.

1.2 With suitable techniques, fission-neutron fluence rates above 10⁹ cm²s¹ can be determined. The ⁶³Cu(n,)⁶⁰Co reaction can be used to determine fast-neutron fluences for irradiation times up to about 15 years (for longer irradiations, see Practice E 261).

1.3 Detailed procedures for other fast-neutron detectors are referenced in Practice E 261.

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.

2. Referenced Documents

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 E 706 (IIB)
E170 Terminology Relating to Radiation Measurements and Dosimetry
E181 Test Methods for Detector Calibration and Analysis of Radionuclides
E261 Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
E844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E 706(IIC)
E944 Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, E 706 (IIA)

Index Terms

activation; activation reaction; copper; cross section; dosimetry; fast-neutron monitor; neutron metrology; pressure vessel surveillance; reaction rate; ICS Number Code 17.240; 27.120.30

Citing ASTM Standards

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