ASTM D5411-21

Standard Practice for Calculation of Average Energy Per Disintegration (<acb><base vertadj="0">E</base><ac>–</ac></acb>) for a Mixture of Radionuclides in Reactor Coolant

SIGNIFICANCE AND USE
5.1 This practice is useful for the determination of the average energy per disintegration of the isotopic mixture found in the reactor-coolant system of a nuclear reactor (1).5 The  value is used to calculate a site-specific activity limit for the reactor coolant system, generally identified as:
   where:  
  K  =   a power reactor site specific constant (usually in the range of 50 to 200).  
The activity of the reactor coolant system is routinely measured, then compared to the value of Alimiting. If the reactor coolant activity value is less than Alimiting then the 2-h radiation dose, measured at the plant boundary, will not exceed an appropriately small fraction of the Code of Federal Regulations, Title 10, part 100 dose guidelines. It is important to note that the measurement of the reactor coolant system radioactivity is determined at a set frequency by use of gamma spectrometry only. Thus, the radionuclides that go into the calculation of  and subsequently Alimiting  are only those that are measured using gamma spectrometry.  
5.2 In calculating , the energy dissipated by beta particles (negatrons and positrons) and photons from nuclear decay of beta-gamma emitters includes the energy released in the form of extra-nuclear transitions such as X-rays, Auger electrons, and conversion electrons. However, not all radionuclides present in a sample are included in the calculation of .  
5.3 Individual nuclear reactor technical specifications vary and each nuclear operator must be aware of limitations affecting plant operation. Typically, iodine radionuclides with half-lives of less than 10 min (except those in equilibrium with the parent) and those radionuclides identified using gamma spectrometry with less than 95 % confidence level are not included in the calculation. However, technical requirements specify that the reported activity must account for at least 95 % of the activity after excluding radioiodines and short-lived radionuclides. There are ind...
SCOPE
1.1 This practice applies to the calculation of the average energy per disintegration ( ) for a mixture of radionuclides in reactor coolant water.  
1.2 The microcurie (µCi) is the standard unit of measurement for this standard. The values given in parentheses are mathematical conversions to SI units, which are provided for information only and are not considered standard.  
1.3 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.  
1.4 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.

General Information

• Status: Published
• Publication Date: 14-Dec-2021
• ICS: 27.120.30 - Fissile materials and nuclear fuel technology
• Technical Committee: D19 - Water
• Drafting Committee: D19.04 - Methods of Radiochemical Analysis

Relations

• Refers: ASTM D7902-20 - Standard Terminology for Radiochemical Analyses
• Effective Date: 01-May-2020

Standards Content (Sample)

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.
Designation: D5411 − 21
Standard Practice for
¯
Calculation of Average Energy Per Disintegration (E) for a
1
Mixture of Radionuclides in Reactor Coolant
This standard is issued under the fixed designation D5411; 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 (´) indicates an editorial change since the last revision or reapproval.
1. Scope 2.2 Code of Federal Regulations:
3
10 CFR 100 Reactor Site Criteria
1.1 This practice applies to the calculation of the average
¯
energy per disintegration (E) for a mixture of radionuclides in
3. Terminology
reactor coolant water.
3.1 Definitions:
1.2 The microcurie (µCi) is the standard unit of measure- 3.1.1 For definitions of terms used in this standard, refer to
ment for this standard. The values given in parentheses are Terminologies D1129 and D7902. For terms not defined in this
mathematical conversions to SI units, which are provided for test method or in Terminologies D1129 and D7902, refer to
4
information only and are not considered standard. other published glossaries.
1.3 This standard does not purport to address all of the
4. Summary of Practice
safety concerns, if any, associated with its use. It is the
¯
4.1 The average energy per disintegration, E (pronounced E
responsibility of the user of this standard to establish appro-
bar), for a mixture of radionuclides is calculated from the
priate safety, health, and environmental practices and deter-
¯
known composition of the mixture. E is computed by calcu-
mine the applicability of regulatory limitations prior to use.
lating the total beta/gamma energy release rate, in MeV, and
1.4 This international standard was developed in accor-
¯
dividing it by the total disintegration rate. The resultant E has
dance with internationally recognized principles on standard-
units of MeV per disintegration.
ization established in the Decision on Principles for the
Development of International Standards, Guides and Recom-
5. Significance and Use
mendations issued by the World Trade Organization Technical
5.1 This practice is useful for the determination of the
Barriers to Trade (TBT) Committee.
average energy per disintegration of the isotopic mixture found
5
¯
in the reactor-coolant system of a nuclear reactor (1). The E
2. Referenced Documents
value is used to calculate a site-specific activity limit for the
2
2.1 ASTM Standards:
reactor coolant system, generally identified as:
D1066 Practice for Sampling Steam
¯
D1129 Terminology Relating to Water
A 5 K/E (1)
limiting
D3370 Practices for Sampling Water from Flowing Process
where:
Streams
K = a power reactor site specific constant (usually in the
D3648 Practices for the Measurement of Radioactivity
range of 50 to 200).
D7282 Practice for Set-up, Calibration, and Quality Control
of Instruments Used for Radioactivity Measurements The activity of the reactor coolant system is routinely
D7902 Terminology for Radiochemical Analyses
measured, then compared to the value of A . If the reactor
limiting
coolantactivityvalueislessthan A thenthe2-hradiation
limiting
dose, measured at the plant boundary, will not exceed an
appropriately small fraction of the Code of Federal
1
This practice is under the jurisdiction ofASTM Committee D19 on Water and
is the direct responsibility of Subcommittee D19.04 on Methods of Radiochemical
Analysis.
3
Current edition approved Dec. 15, 2021. Published February 2022. Originally Available from DLA Document Services, Building 4/D, 700 Robbins Ave.,
approved in 1993. Last previous edition approved in 2015 as D5411 – 10 (2015). Philadelphia, PA 19111-5094, http://quicksearch.dla.mil.
4
DOI: 10.1520/D5411-21. “American National Standard Glossary of Terms,” Nuclear Science and
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or Technology (ANSI N1.1), American National Standards Institute, 1430 Broadway,
contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM New York, NY 10018.
5
Standards volume information, refer to the standard’s Document Summary page on The boldface numbers in parentheses refer to a list of references at the end of
the ASTM website. this practice.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
D5411 − 21
Regulations, Title 10, part 100 dose guidelines. It is important requires some significant time, relative to 10 min, to collect,
to note that the measurement of the reactor coolant sy
...

This document is not an ASTM standard and is intended only to provide the user of an ASTM standard an indication of what changes have been made to the previous version. Because
it may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current version
of the standard as published by ASTM is to be considered the official document.
Designation: D5411 − 10 (Reapproved 2015) D5411 − 21
Standard Practice for
Calculation of Average Energy Per Disintegration (E¯) for a
1
Mixture of Radionuclides in Reactor Coolant
This standard is issued under the fixed designation D5411; 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 (´) indicates an editorial change since the last revision or reapproval.
1. Scope
¯
1.1 This practice applies to the calculation of the average energy per disintegration (E) for a mixture of radionuclides in reactor
coolant water.
1.2 The microcurie (μCi) is the standard unit of measurement for this standard. The values given in parentheses are mathematical
conversions to SI units, which are provided for information only and are not considered standard.
1.3 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.
1.4 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.
2. Referenced Documents
2
2.1 ASTM Standards:
D1066 Practice for Sampling Steam
D1129 Terminology Relating to Water
D3370 Practices for Sampling Water from Flowing Process Streams
D3648 Practices for the Measurement of Radioactivity
D7282 Practice for Set-up, Calibration, and Quality Control of Instruments Used for Radioactivity Measurements
D7902 Terminology for Radiochemical Analyses
2.2 Code of Federal Regulations:
3
10 CFR 100 Reactor Site Criteria
3. Terminology
3.1 Definitions—Definitions: For definitions of terms used in this practice, refer to Terminology D1129.
1
This practice is under the jurisdiction of ASTM Committee D19 on Water and is the direct responsibility of Subcommittee D19.04 on Methods of Radiochemical Analysis.
Current edition approved Dec. 15, 2015Dec. 15, 2021. Published December 2015February 2022. Originally approved in 1993. Last previous edition approved in 20102015
as D5411 – 10.D5411 – 10 (2015). DOI: 10.1520/D5411-10R15.10.1520/D5411-21.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM Standards
volume information, refer to the standard’s Document Summary page on the ASTM website.
3
Available from Standardization Documents Order Desk, Bldg. 4 Section D, DLA Document Services, Building 4/D, 700 Robbins Ave., Philadelphia, PA 19111-5094,
Attn: NPODS.http://quicksearch.dla.mil.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
D5411 − 21
3.1.1 For definitions of terms used in this standard, refer to Terminologies D1129 and D7902. For terms not defined in this test
4
method or in Terminologies D1129 and D7902, refer to other published glossaries.
4. Summary of Practice
¯
4.1 The average energy per disintegration, E (pronounced E bar), for a mixture of radionuclides is calculated from the known
¯
composition of the mixture. E is computed by calculating the total beta/gamma energy release rate, in MeV, and dividing it by the
¯
total disintegration rate. The resultant E has units of MeV per disintegration.
5. Significance and Use
5.1 This practice is useful for the determination of the average energy per disintegration of the isotopic mixture found in the
5
¯
reactor-coolant system of a nuclear reactor (1). The E value is used to calculate a site-specific activity limit for the reactor coolant
system, generally identified asas:
¯
A 5 K/E (1)
limiting
¯
A 5 K/E (1)
limiting
where:
K = a power reactor site specific constant (usually in the range of 50 to 200).
where
K = a power reactor site specific constant (usually in the range of 50 to 200).
The activity of the reactor coolant system is routinely measured, then compared to the value of A . If the reactor coolant
limiting
activity value is less than A then the 2-h radiation dose, measured at the plant boundary, will not exceed an appropriately
limiting
small fraction
...