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ASTM E 343 : 1996

Withdrawn

Withdrawn

A Withdrawn Standard is one, which is removed from sale, and its unique number can no longer be used. The Standard can be withdrawn and not replaced, or it can be withdrawn and replaced by a Standard with a different number.

Standard Test Method for Measuring Reaction Rates by Analysis of Molybdenum-99 Radioactivity From Fission Dosimeters (Withdrawn 2002)

Available format(s)

Hardcopy , PDF

Withdrawn date

05-11-2013

Language(s)

English

Published date

31-12-2010

CONTAINED IN VOL. 12.02, 2001 Covers the measurement of reaction rates by analyzing Molybdenum-99 radioactivity from fission dosimeters.

Committee
E 10
DocumentType
Test Method
Pages
4
PublisherName
American Society for Testing and Materials
Status
Withdrawn

1.1 This test method covers the measurement of reaction rates by determining the amount of the fission product 99 Mo produced by the non-threshold reactions 241 Am(n,f), 235 U(n,f), and 239 Pu(n,f) and by the threshold reactions 238 U(n,f), 237 Np(n,f), and 232 Th(n,f).

1.2 These reactions produce many fission products, among which is 99 Mo, having a half-life of 65.94 h. Because of unresolved or interfering gamma rays when gamma-ray spectrometry is accomplished, the competing activity from other fission products requires that a chemical separation be employed to isolate the 99 Mo. 99 Mo emits gamma rays of several energies, which are easily detected and identified by a gamma-ray spectrometer.

1.3 With suitable techniques, neutron fluence rates can be measured in the range 10 to approximately 10 14 n[dot]cm [dot]s .

1.4 The measurement of time-integrated reaction rates with fission dosimeters by 99 Mo analysis is limited by the half-life of Mo to irradiation times up to about 300 h.

1.5 The values stated in SI units are to be regarded as the 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 and health practices and determine the applicability of regulatory limitations prior to use.

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ASTM E 261 : 2016 : REDLINE Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
ASTM E 261 : 2016 Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
ASTM E 763 : 1991 Practice for Calculation of Absorbed Dose From Neutron Irradiation by Application of Threshold-Foil Measurement Data (Withdrawn 1997)

ASTM E 181 : 2017 : REDLINE Standard Test Methods for Detector Calibration and Analysis of Radionuclides
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ASTM E 170 : 2017 : REDLINE Standard Terminology Relating to Radiation Measurements and Dosimetry
ASTM E 704 : 2013 : REDLINE Standard Test Method for Measuring Reaction Rates by Radioactivation of Uranium-238
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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