ASTM C1233-09

Standard Practice for Determining Equivalent Boron Contents of Nuclear Materials

ABSTRACT
This practice details the recommended method for calculating the equivalent boron content (EBC) values of nuclear elements and materials that are of potential significance as thermal neutron poisons. EBC factors are determined from the atomic weight of elements and the thermal neutron absorption cross section in barns. These may be used depending upon the actual neutron energy characteristics of the applicable reactor system. The elements aluminum, fluorine, rubidium, barium, lead, silicon, beryllium, neon, tin, bismuth, oxygen, zirconium, carbon, magnesium, cerium, and phosphorus are not required to be included in the EBC calculations as their contribution to the total poison effect is not considerably significant.
SCOPE
1.1 This standard details a recommended practice for the calculation of the Equivalent Boron Content (EBC) for nuclear materials. The EBC is used to provide a measure of the macroscopic neutron absorption cross section of a nuclear material. EBC factors for the natural elements are determined from their atomic their masses and thermal neutron absorption cross sections. This practice is illustrated by using EBC factors that are based on thermal neutron (2200 m/s) absorption cross sections. Other EBC factors may be used depending upon the actual neutron energy spectrum.
1.2 The EBC is a characteristic of a homogeneous material. Characterization of inhomogeneous materials and calculation of neutron multiplication factors require techniques that are beyond the scope of this practice.  
1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.

General Information

• Status: Historical
• Publication Date: 31-May-2009
• ICS: 27.120.30 - Fissile materials and nuclear fuel technology
• Technical Committee: C26 - Nuclear Fuel Cycle
• Drafting Committee: C26.02 - Fuel and Fertile Material Specifications

Relations

• Replaces: ASTM C1233-03 - Standard Practice for Determining Equivalent Boron Contents of Nuclear Materials
• Effective Date: 01-Jun-2009
• Referred By: ASTM C799-19 - Standard Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Nuclear-Grade Uranyl Nitrate Solutions
• Effective Date: 01-Jun-2009
• Referred By: ASTM C1462-21 - Standard Specification for Uranium Metal Enriched to Less Than 20 % <sup> 235</sup >U
• Effective Date: 01-Jun-2009
• Referred By: ASTM C1065-08(2022) - Standard Specification for Nuclear-Grade Zirconium Oxide Powder
• Effective Date: 01-Jun-2009
• Referred By: ASTM C781-20 - Standard Practice for Testing Graphite Materials for Gas-Cooled Nuclear Reactor Components
• Effective Date: 01-Jun-2009
• Referred By: ASTM D7301-21 - Standard Specification for Nuclear Graphite Suitable for Components Subjected to Low Neutron Irradiation Dose
• Effective Date: 01-Jun-2009
• Referred By: ASTM C697-16 - Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Plutonium Dioxide Powders and Pellets
• Effective Date: 01-Jun-2009
• Referred By: ASTM C753-16a(2021) - Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
• Effective Date: 01-Jun-2009
• Referred By: ASTM C788-03(2021) - Standard Specification for Nuclear-Grade Uranyl Nitrate Solution or Crystals
• Effective Date: 01-Jun-2009
• Referred By: ASTM C776-17(2022) - Standard Specification for Sintered Uranium Dioxide Pellets for Light Water Reactors
• Effective Date: 01-Jun-2009
• Referred By: ASTM D7219-19 - Standard Specification for Isotropic and Near-isotropic Nuclear Graphites
• Effective Date: 01-Jun-2009
• Referred By: ASTM C757-16(2021) - Standard Specification for Nuclear-Grade Plutonium Dioxide Powder for Light Water Reactors
• Effective Date: 01-Jun-2009
• Referred By: ASTM C1793-15 - Standard Guide for Development of Specifications for Fiber Reinforced Silicon Carbide-Silicon Carbide Composite Structures for Nuclear Applications
• Effective Date: 01-Jun-2009
• Referred By: ASTM C1783-15 - Standard Guide for Development of Specifications for Fiber Reinforced Carbon-Carbon Composite Structures for Nuclear Applications
• Effective Date: 01-Jun-2009
• Referred By: ASTM C785-08(2022) - Standard Specification for Nuclear-Grade Aluminum Oxide Pellets
• Effective Date: 01-Jun-2009

Standards Content (Sample)

NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Contact ASTM International (www.astm.org) for the latest information
Designation: C1233 − 09
StandardPractice for
Determining Equivalent Boron Contents of Nuclear
1
Materials
This standard is issued under the fixed designation C1233; 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 3. Methods For EBC Determination
1.1 This standard details a recommended practice for the
3.1 Agreement shall be reached between the buyer and
calculation of the Equivalent Boron Content (EBC) for nuclear
seller as to which elements shall be analyzed for calculation of
materials. The EBC is used to provide a measure of the
their EBC. It is recommended that B, Cd, Dy, Eu, Sm, and Gd
macroscopic neutron absorption cross section of a nuclear
be included in this calculation. Analytical methods for such
material. EBC factors for the natural elements are determined
elements shall be those given in Test Methods C696, C698,
from their atomic masses and thermal neutron absorption cross
C761, and C799 as applicable or as otherwise agreed upon
sections. This practice is illustrated by using EBC factors that
between buyer and seller.
are based on thermal neutron (2200 m/s) absorption cross
3.2 TheindividualEBCvaluesarecalculatedusingtheEBC
sections. Other EBC factors may be used depending upon the
factors from Table 1 as follows:
actual neutron energy spectrum.
1.2 The EBC is a characteristic of a homogeneous material.
EBC of constituent =
Characterization of inhomogeneous materials and calculation
(EBC factor of constituent)(µg of constituent/gof material)
of neutron multiplication factors require techniques that are
where:
beyond the scope of this practice.
EBC factor of constituent = (atomic mass of boron)(σaof
1.3 The values stated in SI units are to be regarded as
constituent)/[(atomic mass of constituent)(σa of boron)], and
standard. No other units of measurement are included in this σa = atomic neutron absorption cross section in barns.
standard.
The EBC factors been calculated using a value of 764 barns
for the neutron absorption cross section (σa) of boron. This
2. Referenced Documents
value may vary in nature according to the isotopic composition
2
2.1 ASTM Standards:
of the elements. If an alternative value is chosen the EBC
C696 Test Methods for Chemical, Mass Spectrometric, and
factors must be recalculated using the chosen value.
Spectrochemical Analysis of Nuclear-Grade Uranium Di-
3.3 If the concentration of any of the elements used in the
oxide Powders and Pellets
calculation is reported as “less than” values, these values shall
C698 Test Methods for Chemical, Mass Spectrometric, and
be used in calculating the EBC.
Spectrochemical Analysis of Nuclear-Grade Mixed Ox-
ides ((U, Pu)O )
2 3.4 A total EBC value, if required, is determined by the
C761 Test Methods for Chemical, Mass Spectrometric,
summation of individual EBC values.
Spectrochemical, Nuclear, and RadiochemicalAnalysis of
3.5 Plutonium and uranium have not been included, as they
Uranium Hexafluoride
are fissionable elements.
C799 Test Methods for Chemical, Mass Spectrometric,
Spectrochemical, Nuclear, and RadiochemicalAnalysis of
3.6 Table 1 includes elements that may provide a negligible
Nuclear-Grade Uranyl Nitrate Solutions
contribution to the total EBC. In particular, elements with both
small concentrations and very small EBC factors (less than
1 2E-4) will generally provide a negligible contribution to the
This practice is under the jurisdiction of ASTM Committee C26 on Nuclear
Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fuel and
EBC of the material as a whole. Such elements should be
Fertile Material Specifications.
excluded from determinations of the total EBC.
CurrenteditionapprovedJune1,2009.PublishedJuly2009.Originallyapproved
in 1993. Last previous approved in 2003 as C1233 – 03. DOI: 10.1520/C1233-09.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or 4. Keywords
contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
4.1 boron; neutron absorption; nuclear materials; nuclear
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website. poisons
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

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C1233 − 09
TABLE 1 Equivalent Boron Content Factors
A
Neutron Absorption Cross Section B
Element Atomic Mass EBC Factor
(Barns) at 2200 m/s
C
Aluminium 0.231 26.98 1.21E-04
D
Antimony 5.1 121.75 5.93E-04
Argon 0.68 39.95 2.41E-04
Arsenic 4.5 74.92 8.50E-04
C D
Barium 1.2 137.33 1.24E-04
C D
Beryl
...

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:C1233–03 Designation:C1233–09
Standard Practice for
Determining Equivalent Boron Contents of Nuclear
1
Materials
This standard is issued under the fixed designation C 1233; 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
1.1This standard details a recommended practice for the calculation of the Equivalent Boron Content (EBC) values for elements
that are of potential significance as thermal neutron poisons. The values are determined from a knowledge of the atomic weight
of elements and the thermal neutron absorption cross section in barns.This practice is illustrated by using the EBC factors ofTable
1 which are based on thermal neutron (2200 m/s) absorption cross sections. Other EBC factors may be used depending upon the
actual neutron energy characteristics of the applicable reactor system.
1.2The following elements do not require to be included in the EBC calculations, as their EBC factors are less than or equal
to 0.0001.
aluminum fluorine rubidium
barium lead silicon
beryllium neon tin
bismuth oxygen zirconium
carbon magnesium
cerium phosphorus
Their contribution to the total poison effect is not considered significant.
1.1 This standard details a recommended practice for the calculation of the Equivalent Boron Content (EBC) for nuclear
materials. The EBC is used to provide a measure of the macroscopic neutron absorption cross section of a nuclear material. EBC
factors for the natural elements are determined from their atomic their masses and thermal neutron absorption cross sections. This
practice is illustrated by using EBC factors that are based on thermal neutron (2200 m/s) absorption cross sections. Other EBC
factors may be used depending upon the actual neutron energy spectrum.
1.2 The EBC is a characteristic of a homogeneous material. Characterization of inhomogeneous materials and calculation of
neutron multiplication factors require techniques that are beyond the scope of this practice.
1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
2. Referenced Documents
2
2.1 ASTM Standards:
C 696 Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide
Powders and Pellets
C 698 Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Mixed Oxides ((U,
Pu)O )
2
C699Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of, and Physical Tests on, Beryllium Oxide
2
Powder
C 761 Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Uranium
Hexafluoride
C 799 Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Nuclear-
2
Grade Uranyl Nitrate Solutions
2
C859Terminology Relating to Nuclear Materials Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear,
and Radiochemical Analysis of Nuclear-Grade Uranyl Nitrate Solutions
1
This practice is under the jurisdiction of ASTM Committee C26 on Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fuel and Fertile
Material Specifications.
Current edition approved July 10, 2003. Published August 2003. Originally approved in 1993. Last previous approved in 1998 as C1233–98.
Current edition approved June 1, 2009. Published July 2009. Originally approved in 1993. Last previous approved in 2003 as C 1233 – 03.
2
For referencedASTM standards, visit theASTM website, www.astm.org, or contactASTM Customer Service at [e-mail]. For Annual Book of ASTM Standards
, Vol 12.01.volume information, refer to the standard’s Document Summary page on the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
1

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C1233–09
3. Terminology
3.1Terms shall be defined in accordance with Terminology C859.
4.Methods For EBC Determination
43.1 Agreement shall be reached between the buyer and seller as to which elements shall be analyzed for calculation of their
EBC. It is recommended that B, Cd, Dy, Eu, Sm, and Gd be included in this calculation. Analytical methods for such elements
shall be those given in Test Methods C696, C699, and C799C 696, C
...