ASTM E263-18

5.1 Refer to Guide E844 for guidance on the selection, irradiation, and quality control of neutron dosimeters.

5.2 Refer to Practice E261 for a general discussion of the determination of fast-neutron fluence rate with threshold detectors.

5.3 Pure iron in the form of foil or wire is readily available and easily handled.

5.4 Fig. 1 shows a plot of cross section as a function of neutron energy for the fast-neutron reaction ⁵⁴Fe(n,p)⁵⁴Mn FIG. 1 ⁵⁴Fe(n,p)⁵⁴Mn Cross Section

5.5 ⁵⁴Mn has a half-life of 312.19 (3) days5.6 Interfering activities generated by neutron activation arising from thermal or fast neutron interactions are 2.57878 (46)-h ⁵⁶Mn, 44.494 (12) days ⁵⁹Fe, and 5.2711 (8) years ⁶⁰Co (2,3). (Consult the latest version of Ref 5.7 The vapor pressures of manganese and iron are such that manganese diffusion losses from iron can become significant at temperatures above about 700°C. Therefore, precautions must be taken to avoid the diffusion loss of ⁵⁴Mn from iron dosimeters at high temperature. Encapsulating the iron dosimeter in quartz or vanadium will contain the manganese at temperatures up to about 900°C.

5.8 Sections 6, 7 and 8 that follow were specifically written to describe the method of chemical separation and subsequent counting of the ⁵⁴Mn activity. When one elects to count the iron dosimeters directly, those portions of Sections 6, 7 and 8 that pertain to radiochemical separation should be disregarded.

1.1 This test method describes procedures for measuring reaction rates by the activation reaction ⁵⁴Fe(n,p)⁵⁴Mn.

1.2 This activation reaction is useful for measuring neutrons with energies above approximately 2.2 MeV and for irradiation times up to about three years, provided that the analysis methods described in Practice E261 are followed. If dosimeters are analyzed after irradiation periods longer than three years, the information inferred about the fluence during irradiation periods more than three years before the end of the irradiation should not be relied upon without supporting data from dosimeters withdrawn earlier.

1.3 With suitable techniques, fission-neutron fluence rates above 10⁸ cm⁻²·s⁻¹ can be determined. However, in the presence of a high thermal-neutron fluence rate (for example, >2 × 10¹⁴ cm⁻²·s ⁻¹) ⁵⁴Mn depletion should be investigated.

1.4 Detailed procedures describing the use of other fast-neutron detectors are referenced in Practice E261.

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

1.6 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.

1.7 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.