ASTM E704-96

Standard Test Method for Measuring Reaction Rates by Radioactivation of Uranium-238

SCOPE
1.1 This test method covers procedures for measuring reaction rates by assaying a fission product (F.P.) from the fission reaction  238 U(n,f)F.P.  
1.2 The reaction is useful for measuring neutrons with energies from approximately 1.5 to 7 MeV and for irradiation times up to 30 to 40 years.  
1.3 Equivalent fission neutron fluence rates as defined in Practice E261 can be determined.  
1.4 Detailed procedures for other fast-neutron detectors are referenced in Practice E261.  
1.5 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: Historical
• Publication Date: 31-Dec-1995
• Technical Committee: E10 - Nuclear Technology and Applications
• Drafting Committee: E10.05 - Nuclear Radiation Metrology

Relations

• Replaced By: ASTM E704-96(2002) - Standard Test Method for Measuring Reaction Rates by Radioactivation of Uranium-238
• Effective Date: 10-Jan-1996

Standards Content (Sample)

Designation: E 704 – 96
AMERICAN SOCIETY FOR TESTING AND MATERIALS
100 Barr Harbor Dr., West Conshohocken, PA 19428
Reprinted from the Annual Book of ASTM Standards. Copyright ASTM
Standard Test Method for
Measuring Reaction Rates by Radioactivation of Uranium-
1
238
This standard is issued under the fixed designation E 704; 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.
2
1. Scope ment Methods in Reactor Surveillance, (IIA)
E 1005 Test Method for Application and Analysis of Radio-
1.1 This test method covers procedures for measuring reac-
metric Monitors for Reactor Vessel Surveillance, E706
tion rates by assaying a fission product (F.P.) from the fission
2
238
(IIIA)
reaction U(n,f)F.P.
E 1018 Guide for Application of ASTM Evaluated Cross
1.2 The reaction is useful for measuring neutrons with
2
Section Data File, Matrix E 706 (IIB)
energies from approximately 1.5 to 7 MeV and for irradiation
times up to 30 to 40 years.
3. Terminology
1.3 Equivalent fission neutron fluence rates as defined in
3.1 Definitions:
Practice E 261 can be determined.
3.1.1 Refer to Terminology E 170.
1.4 Detailed procedures for other fast-neutron detectors are
referenced in Practice E 261.
4. Summary of Test Method
1.5 This standard does not purport to address all of the
238 235
4.1 High-purity U (<40 ppm U) is irradiated in a
safety concerns, if any, associated with its use. It is the
fast-neutron field, thereby producing radioactive fission prod-
responsibility of the user of this standard to establish appro-
238
ucts from the reaction U(n,f)F.P.
priate safety and health practices and determine the applica-
137 137m 140
4.2 Various fission products such as Cs- Ba, Ba-
bility of regulatory limitations prior to use.
140 95 144
La, Zr, and Ce can be assayed depending on the length
of irradiation, purpose of the experiment, etc.
2. Referenced Documents
4.3 The gamma rays emitted through radioactive decay are
2.1 ASTM Standards:
counted, and the reaction rate, as defined in Practice E 261, is
E 170 Terminology Relating to Radiation Measurements
2
calculated from the decay rate and the irradiation conditions.
and Dosimetry
4.4 The neutron fluence rate for neutrons with energies from
E 181 Test Methods for Detector Calibration and Analysis
2
approximately 1.5 to 7 MeV can then be calculated from the
of Radionuclides
spectral-weighted neutron activation cross section as defined in
E 261 Practice for Determining Neutron Fluence Rate, Flu-
2
Practice E 261.
ence, and Spectra by Radioactivation Techniques
237 238
4.5 A parallel procedure that uses Np instead of Uis
E 262 Test Method for Determining Thermal Neutron Re-
2
given in Test Method E 705.
action and Fluence Rates by Radioactivation Techniques
E 320 Test Methods for Cesium-137 in Nuclear Fuel Solu-
5. Significance and Use
2
tions by Radiochemical Analysis
5.1 Refer to Practice E 261 for a general discussion of the
E 393 Test Method for Measuring Reaction Rates by Analy-
2 determination of fast-neutron fluence rate with fission detec-
sis of Barium-140 from Fission Dosimeters
tors.
E 482 Guide for Application of Neutron Transport Methods
238
2 5.2 U is available as metal foil, wire, or oxide powder
for Reactor Vessel Surveillance, E706 (IID)
(see Guide E 844). It is usually encapsulated in a suitable
E 705 Test Method for Measuring Reaction Rates by Ra-
238
2 container to prevent loss of, and contamination by, the U
dioactivation of Neptunium-237
3
and its fission products.
E 844 Guide for Sensor Set Design and Irradiation for
2 5.3 One or more fission products can be assayed. Pertinent
Reactor Surveillance, E706 (IIC)
data for relevant fission products are given in Table 1 and Table
E 944 Guide for Application of Neutron Spectrum Adjust-
2.
137 137m
5.3.1 Cs- Ba is chosen frequently for long irradia-
1 134 136
This test method is under the jurisdiction of ASTM Committee E-10 on Nuclear
tions. Radioactive products Cs and Cs may be present,
Technology and Applicationsand is the direct responsibility of Subcommittee
E10.05on Nuclear Radiation Metrology.
Current edition approved Jan. 10, 1996. Published March 1996. Originally
3
published as E 704 – 84. Last previous edition E 704 – 90. Vanadium-encapsulated monitors of high purity are available from the Oak
2
Annual Book of ASTM Standards, Vol 12.02. Ridge National Laboratory, Isotope Sales Div., Oak Ridge, TN 37830.
1

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E 704
TABLE 1 Recommended Nuclear Parameters for Certain Fission
research-reactor cores, can be large for deep-water penetrations
Products 4
(1).
Maximum
5.5 Good agreement between neutron fluence measured by
Primary g Probability
Fission Parent Useful
A 238 54 54
Radiation of
U fission and the Fe(n,p) Mn reaction has been demon-
A
...