ASTM E264-92

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

General Information

• Status: Historical
• Publication Date: 31-Dec-1991
• Technical Committee: E10 - Nuclear Technology and Applications
• Drafting Committee: E10.05 - Nuclear Radiation Metrology

Standards Content (Sample)

ASTM E264 92 m 0759530 0537263 442 m
AMERICAN SOCIETY FOR TESTING AND MATERIALS
di)) Designation: E 264 - 92
1916 Race St Philadelphla, Pa 19103
Reprlnted from Uie Amua1 Book of ASTM Standards. Copyright ASTM
If not listed in the current comblned index, will appear in the nexi edthn.
Standard Test Method for
Measuring Fast-Neutron Reaction Rates by Radioactivation of
Nickel’
This standard is issued under the fixed designation E 264; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (0 indicates an editorial change since the last revision or reapproval.
This standard has been approved& use by agencies o$ the Department o$De/ense. Consult the DoD Index oJSpecijications and
Siandardsior the specijic year osissue which has been adopted by the Department o$De/ense.
4. Summary of Test Method
1. Scope
4.1 High-purity nickel is irradiated in a neutron field
1.1 This test method describes procedures for measuring
reaction rates by the activation reaction s8Ni(n,p) To. thereby producing radioactive 58C0 from the 58Ni(n,p) s8Co
1.2 This activation reaction is useful for measuring neu- activation reaction.
trons with energies above approximately 2.1 MeV and for
4.2 The gamma rays emitted by the radioactive decay of
irradiation times up to about 200 days in the absence of high
Wo are counted in accordance with Methods E 18 1 and the
thermal neutron fluence rates (for longer irradiations, see
reaction rate, as defined by Test Method E 26 1, is calculated
Test Method E 261).
from the decay rate and irradiation conditions.
1.3 Withwitable techniques fission-neutron fluence rates
4.3 The neutron fluence rate above about 2.1 MeV can
densities above lo7 cm’2-s-1 can be determined.
then be calculated from the spectral-weighted neutron acti-
1.4 Detailed procedures for other fast-neutron detectors
vation cross section as defined by Test Method E 26 1.
are referenced in Test Method E 26 1.
1.5 This standard does not purport to address all of the
If any, associated with its use. It is the
safery problems,
5. Significance and Use
responsibility of the user of this standard to establish appro-
5.1 Refer to Guide E 844 for the selection, irradiation,
priate safety and health practices and determine the applica-
and quality control of neutron dosimeters.
bilily of regulalory limitations prior to use.
5.2 Refer to Test Method E 26 1 for a general discussion of
the determination of fast-neutron fluence rate with threshold
2. Referenced Documents
detectors.
ASTM Standards: 5.3 Pure nickel in the form of foil or wire is readily
2.1
E 170 Terminology Relating to Radiation Measurements
available, and easily handled.
and Dosimetry2
5.4 Yo has a half-life of 70.82 days and emits a gamma
E 181 General Methods for Detector Calibration and
ray with an energy of 0.8108-MeV.3
Analysis of Radionuclides*
5.5 Competing activities 65Ni(2.52 h) and 57Ni(36. 1 h) are
1 Test Method for Determining Neutron Fluence
E 26
formed by the reactions 64Ni(n,y) 65Ni, and s8Ni(n,2n) 57Ni,
Rate, Fluence, and Spectra by Radioactivation
respectively.
Techniques2
5.6 A second 9.15-h isomer, 58mC~, is formed that decays
E 844 Guide for Sensor Set Design and Irradiation for
to 70.82-day %o, Loss of 58C0 and 58mC~ by thermal-
Reactor Surveillance2
neutron burnout will occur in environments having thermal
E 944 Guide for Application of Neutron Spectrum Ad-
fluence rates of 3 x 10” cm-2.s-1 and above. The 58Co(n,y)
justment Methods in Reactor Surveillance’
59C0 and 58mC~(n,y) 59C0 cross sections have been measured
E 1005 Test Method for Application and Analysis of
at 1650 and 1.4 x 10’ barns, re~pectively.~ Burnout correc-
Radiometric Monitors for Reactor Vessel Surveillance’
tion factors, R, are plotted as a function of time for several
E 1018 Guide for Application of ASTM Evaluated Nu-
thermal fluxes in Fig. 2.
clear Data File (ENDF/A)-Cross Section and Uncer-
5.7 Figure 1 shows a plot of cross section versus energy for
tainty File2
the fast-neutron reaction 58Ni(n,p) 58C0.5 This figure is for
illustrative purposes only to indicate the range of response of
3. Terminology
the.58Ni(n,p) reaction. Refer to Guide E 1018 for descrip-
3.1 DeJinitions:
tions of recommended tabulated dosimetry cross sections.
3.1.1 Refer to Terminology E 170.
“Nuclear Data SheetsJor A = 58,” National Nuclear Data Center, Vol 42,
I This test method is under the jurisdiction of ASTM Committee E-IO on 1984, p. 457.
Nuclear Technology and Applications and is the direct responsibility of Subcom- Hom, C. H., Weber, L. D., and Yates, E. C., “isomers and the Effects on Fast
mittee E10.05 on Nuclear Radiation Metrology. Flux Measurements Using Nickel,” Aiotnic Energy Commission R and D Report
Current edition approved Oct. 15, 1992. Pub
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