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ASTM E264-19
Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Nickel
NORMA vydaná dňa 1.4.2019
Informácie o norme:
Označenie normy: ASTM E264-19
Dátum vydania normy: 1.4.2019
Kód tovaru: NS-948767
Počet strán: 4
Približná hmotnosť: 12 g (0.03 libier)
Krajina: Americká technická norma
Kategória: Technické normy ASTM
Kategórie - podobné normy:
Anotácia textu normy ASTM E264-19 :
Keywords:
activation, activation reaction, cross section, dosimetry, fast-neutron monitor, neutron metrology, nickel, pressure vessel surveillance, reaction rate,, ICS Number Code 17.240 (Radiation measurements),27.120.30 (Fissile materials and nuclear fuel technology)
Doplňujúce informácie
| Significance and Use | ||||||||||||||
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5.1 Refer to Guide E844 for 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 nickel in the form of foil or wire is readily available, and easily handled. 5.4 58Co has a half-life of 70.85 (3) days (Refs 5.5 Competing activities 65Ni(2.5172 h) and 57Ni(35.9 (3) h (Ref 5.6 A second 9.04 h isomer, 58mCo, is formed that decays to 70.85-day 58Co. Loss of 58Co and 58mCo by thermal-neutron burnout will occur in environments (Refs 5.7 Fig. 2 shows a plot of cross section (Ref (6)) versus energy for the fast-neutron reaction 58Ni(n,p) 58Co. This figure is for illustrative purposes only to indicate the range of response of the 58Ni(n,p) reaction. Refer to Guide E1018 for descriptions of recommended tabulated dosimetry cross sections. FIG. 2 58Ni(n,p)58Co Cross Section Note 1: The data is taken from the Evaluated Nuclear Data
File, ENDF/B-VI, rather than the later ENDF/B-VII. This is in
accordance with E1018,
section 6.1, since the later ENDF/B-VII data files do not include
covariance information. For more details see Section H of Ref
1.1 This test method covers procedures
for measuring reaction rates by the activation reaction
58Ni(n,p)58Co.
FIG. 1 Note 1: The burnup corrections were computed using effective burn-up cross sections of 1650 b for 58Co(n,γ) and 1.4E5 b for 58mCo(n,γ). 1.2 This activation reaction is useful for measuring neutrons with energies above approximately 2.1 MeV and for irradiation times up to about 200 days in the absence of high thermal neutron fluence rates, provided that the analysis methods described in Practice E261 are followed. If dosimeters are analyzed after irradiation periods longer than 200 days, the information inferred about the fluence during irradiation periods more than 200 days 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 densities above 107 cm−2·s −1 can be determined. 1.4 Detailed procedures for 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. |
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