Standard Test Method for Measuring Reaction Rates by Analysis of Molybdenum-99 Radioactivity From Fission Dosimeters (Withdrawn 2002)

SCOPE
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.

General Information

Status
Withdrawn
Publication Date
31-Dec-1995
Withdrawal Date
09-Jun-2002
Current Stage
Ref Project

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ASTM E343-96 - Standard Test Method for Measuring Reaction Rates by Analysis of Molybdenum-99 Radioactivity From Fission Dosimeters (Withdrawn 2002)
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Standards Content (Sample)

Designation: E 343 – 96
Standard Test Method for
Measuring Reaction Rates by Analysis of Molybdenum-99
1
Radioactivity From Fission Dosimeters
This standard is issued under the fixed designation E 343; 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 (e) indicates an editorial change since the last revision or reapproval.
1. Scope E 181 Test Methods for Detector Calibration and Analysis
4
of Radionuclides
1.1 This test method covers the measurement of reaction
99
E 261 Practice for Determining Neutron Fluence Rate, Flu-
rates by determining the amount of the fission product Mo
4
241 235
ence, and Spectra by Radioactivation Techniques
produced by the non-threshold reactions Am(n,f), U(n,f),
239
238
E 704 Test Method for Measuring Reaction Rates by Ra-
and Pu(n,f) and by the threshold reactions U(n,f),
4
237 232
dioactivation of Uranium-238
Np(n,f), and Th(n,f).
E 705 Test Method for Measuring Reaction Rates by Ra-
1.2 These reactions produce many fission products, among
4
99
dioactivation of Neptunium-237
which is Mo, having a half-life of 65.94 h. Because of
E 844 Guide for Sensor Set Design and Irradiation for
unresolved or interfering gamma rays when gamma-ray spec-
4
Reactor Surveillance, E706(IIC)
trometry is accomplished, the competing activity from other
E 944 Guide for Application of Neutron Spectrum Adjust-
fission products requires that a chemical separation be em-
4
99 99
ment Methods in Reactor Surveillance (IIA)
ployed to isolate the Mo. Mo emits gamma rays of several
E 1005 Test Method for Application and Analysis of Radio-
energies, which are easily detected and identified by a gamma-
metric Monitors for Reactor Vessel Surveillance,
ray spectrometer.
4
E706(IIIA)
1.3 With suitable techniques, neutron fluence rates can be
7 14 −2 −1
E 1018 Guide for Application of ASTM Evaluated Cross
measured in the range 10 to approximately 10 n·cm ·s .
4
Section Data File, Matrix E 706 (IIB)
1.4 The measurement of time-integrated reaction rates with
99
2.2 Other Document:
fission dosimeters by Mo analysis is limited by the half-life
99
NCRP Handbook of Radioactivity Measurements Proce-
of Mo to irradiation times up to about 300 h.
5
dures, NCRP Report No. 58.
1.5 The values stated in SI units are to be regarded as the
standard.
3. Terminology
1.6 This standard does not purport to address all of the
3.1 Definitions:
safety concerns, if any, associated with its use. It is the
3.1.1 Refer to Terminology E 170.
responsibility of the user of this standard to establish appro-
priate safety and health practices and determine the applica-
4. Summary of Test Method
bility of regulatory limitations prior to use.
99
4.1 The fission product Mo is separated from the irradi-
ated fission dosimeter by a solvent extraction technique. The
2. Referenced Documents
99
activity of the Mo is determined by counting the 740 or 778
2.1 ASTM Standards:
keV, or both, gamma-energy peaks. This information combined
C 697 Test Methods for Chemical, Mass Spectrometric, and
99
with the fission yield of Mo gives the reaction (fission) rate.
Spectrochemical Analysis of Nuclear-Grade Plutonium
2 When the proper cross section is used with the reaction rate,
Dioxide Powders and Pellets
3 the equivalent fission rate can be determined.
D 1193 Specification for Reagent Water
E 170 Terminology Relating to Radiation Measurements
5. Significance and Use
4
and Dosimetry
5.1 Refer to Guide E 844 for the selection, irradiation, and
quality control of neutron dosimeters.
5.2 Refer to Practice E 261 for a general discussion of the
1
measurement of neutron fluence rate and fluence. The neutron
This test method is under the jurisdiction of ASTM Committee E-10 on Nuclear
Technology and Applicationsand is the direct responsibility of Subcommittee
spectrum must be known in order to measure neutron fluence
E10.05 on Nuclear Radiation Metrology.
rates with a single detector. Also it is noted that cross sections
Current edition approved Jan. 10, 1996. Published February 1996. Originally
published as E 343 – 67 T. Last previous edition E 343 – 92.
2
Annual Book of ASTM Standards, Vol 12.01.
3
5
Annual Book of ASTM Standards, Vol 11.01.
Available from National Council on Radiation Protection and Measurements
4
Annual Book of ASTM Standards, Vol 12.02.
(NCRP), 7910 Woodmont Ave., Suite 800, Bethesda, MD 20814.
Copyright © ASTM, 100 Barr Harbor Drive, West Conshohocken, PA 19428-2959, United States.
1

---------------------- Page: 1 ----------------------
E 343
99
TABLE 1 Recommended Cumulative Fission Yields for Mo
Production
Fission Thermal or Fast Fission Yield,
AB
Dosimeter Neutron Field (%)
235
U T 6.18839 6 1.4 %
F 5.91653 6 1.4 %
238
U F 6.18839 6 1.4 %
239
Pu T 6.19863 6 1.4 %
F 5.95472 6 2%
237
Np F 6.11547 6 4%
232
Th F 2.95528 6 2%
241
Am T 6.63629 6 2.8 %
F 5.40483 6 6%
A
These ENDF/B-VI valu
...

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