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ASTM C1233-98

(Practice)

Standard Practice for Determining Equivalent Boron Contents of Nuclear Materials

Standard Practice for Determining Equivalent Boron Contents of Nuclear Materials

SCOPE
1.1 This 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 of Table 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.1.2 The 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.

General Information

Status
Historical
Publication Date
09-Aug-1998
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
Current Stage
Ref Project

Relations

Replaced By
ASTM C1233-03 - Standard Practice for Determining Equivalent Boron Contents of Nuclear Materials
Effective Date
10-Jul-2003

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ASTM C1233-98 - Standard Practice for Determining Equivalent Boron Contents of Nuclear Materials
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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NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.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: C 1233 – 98
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 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 (e) indicates an editorial change since the last revision or reapproval.
1. Scope C 799 Test Methods for Chemical, Mass Spectrometric,
Spectrochemical, Nuclear, and Radiochemical Analysis of
1.1 This standard details a recommended practice for the
2
Nuclear-Grade Uranyl Nitrate Solutions
calculation of the Equivalent Boron Content (EBC) values for
2
C 859 Terminology Relating to Nuclear Materials
elements that are of potential significance as thermal neutron
poisons. The values are determined from a knowledge of the
3. Terminology
atomic weight of elements and the thermal neutron absorption
3.1 Terms shall be defined in accordance with Terminology
cross section in barns. This practice is illustrated by using the
C 859.
EBC factors of Table 1 which are based on thermal neutron
(2200 m/s) absorption cross sections. Other EBC factors may
4. Methods For EBC Determination
be used depending upon the actual neutron energy character-
4.1 Agreement shall be reached between the buyer and
istics of the applicable reactor system.
seller as to which elements shall be analyzed for calculation of
1.2 The following elements do not require to be included in
their EBC. Analytical methods for such elements shall be those
the EBC calculations, as their EBC factors are less than or
given in Methods C 696, C 699, and C 799, and Test Methods
equal to 0.0001.
C 698 and C 761 as applicable or as otherwise agreed upon
aluminum fluorine rubidium
between buyer and seller.
barium lead silicon
beryllium neon tin
4.2 The individual EBC values are calculated using the EBC
bismuth oxygen zirconium
factors from Table 1 as follows:
carbon magnesium
cerium phosphorus
EBC of impurity 5 ~EBC factor!~μg of impurity/g base material!
Their contribution to the total poison effect is not considered
where:
significant.
EBC factor 5 ~atomic mass boron!~sa impurity!
~atomic mass impurity!~sa boron!, and
2. Referenced Documents
sa 5 atomic neutron absorption cross section in
2.1 ASTM Standards:
barns.
C 696 Test Methods for Chemical, Mass Spectrometric, and
The values given in Table 1 have been calculated using a
Spectrochemical Analysis of Nuclear-Grade Uranium Di-
value of 764 Barns for the neutron absorption cross section
2
oxide Powders and Pellets
(sa) of boron. This value may vary in nature according to the
C 698 Test Methods for Chemical, Mass Spectrometric, and
isotopic composition of the elements. If an alternative value is
Spectrochemical Analysis of Nuclear-Grade Mixed Oxides
chosen the EBC factors must be recalculated using the chosen
2
((U,Pu)O )
2
value.
C 699 Methods for Chemical, Mass Spectrometric, and
4.3 If the concentration of any of the elements used in the
Spectrochemical Analysis of, and Physical Tests on, Be-
calculation is reported as “less than” values, these values shall
2
ryllium Oxide Powder
be used in calculating the EBC.
C 761 Test Methods for Chemical, Mass Spectrometric,
4.4 A total EBC value, if required, is determined by the
Spectrochemical, Nuclear, and Radiochemical Analysis of
summation of individual EBC values.
2
Uranium Hexafluoride
4.5 Plutonium, thorium and uranium have not been in-
cluded, as they are fissionable elements.
1
This practice is under the jurisdiction of ASTM Committee C-26 on Nuclear
Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fuel and
5. Keywords
Fertile Material Specifications.
5.1 boron; neutron absorption; nuclear materials; nuclear
Current edition approved Aug. 10, 1998. Published November 1998. Originally
published as C 1233–93. Last previous edition C1233–97. poisons
2
Annual Book of ASTM Standards, Vol 12.01.
1

---------------------- Page: 1 ----------------------
NOTICE:¬This¬standard¬has¬either¬been¬superceded¬and¬replaced¬by¬a¬new¬version¬or¬discontinued.¬
Contact¬ASTM¬International¬(www.astm.org)¬for¬the¬latest¬information.¬
C 1233
TABLE 1 Equivalent Boron Content Factors
A B
Element Neutron Absorption Cross Section (Barns) at 2200 m/s Atomic Mass EBC Factor
C
Antimony 5.1 121.75 0.0006
Argon 0.68 39.95 0.0002
Arsenic 4.5 74.92 0.0008
D
Boron 764 10.81 1.0000
Bromine 6.9 79.91 0.0012
Cadmium 2520 112.41 0.3172
Calcium 0.43 40.08 0.0002
Cesium 29 132.91 0.0031
Chlorine 33.5 35.45 0.0132
Chromium 3.07 52.00 0.0008
Cobalt 37.2 58.93 0.0089
Copper 3.78 63.54 0.0
...

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9  
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10  
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18  
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This specification covers finished sintered and ground (uranium-plutonium) dioxide pellets for use in thermal reactors. It applies to uranium-plutonium dioxide pellets containing plutonium additions up to 15 % weight. The diversity of manufacturing methods shall be recognized by which uranium-plutonium dioxide pellets are produced and the many special requirements for chemical and physical characterization that may be imposed by the operating conditions to which the pellets will be subjected in specific reactor systems. The following are different chemical requirements that shall be determined: uranium content, plutonium content, impurity content, stoichiometry, moisture content, gas content, and americium-241 content. Nuclear requirements such as isotopic content, plutonium equivalent at a given date, equivalent boron content, and reactivity shall also be determined. Physical properties of the pellets like dimensions, density, grain size, pore morphology, plutonium-oxide homogeneity, plutonium-oxide particle size, plutonium-oxide particle distribution, integrity, and surface cracks shall be determined as well. The surfaces of finished pellets shall be visually free of loose chips, oil, macroscopic inclusions, and foreign materials. An estimate of the fuel pellet irradiation stability shall be obtained unless adequate allowance for such effects are factored into the fuel rod design. The estimate of the stability shall consist of either conformance to the thermal stability test as specified in the or by adequate correlation of manufacturing process or microstructure to in-reactor behavior, or both.
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4.1 Materials handling equipment operability and long-term integrity are concerns that originate during the design and fabrication sequences. Such concerns are most efficiently addressed during one or the other of these stages. Equipment operability and integrity can be compromised during handling and installation sequences. For this reason, the subject equipment should be handled and installed under closely controlled and supervised conditions.  
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SCOPE
1.1 This practice covers dissolution treatments for uranium materials that are applicable to the test methods used for characterizing these materials for uranium elemental, isotopic, and impurities determinations. Dissolution treatments for the major uranium materials assayed for uranium or analyzed for other components are listed.  
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Procedure Title  
Section  
Dissolution of Uranium Metal and Oxide with Nitric Acid  
8.1  
Dissolution of Uranium Oxides with Nitric Acid and Residue
Treatment  
8.2  
Dissolution of Uranium-Aluminum Alloys in Hydrochloric Acid
with Residue Treatment  
8.3  
Dissolution of Uranium Scrap and Ash by Leaching with Nitric
Acid and Treatment of Residue by Carbonate Fusion  
8.4  
Dissolution of Refractory Uranium-Containing Material by
Carbonate Fusion  
8.5  
Dissolution of Uranium—Aluminum Alloys
Uranium Scrap and Ash, and Refractory
Uranium-Containing Materials by
Microwave Treatment  
8.6  
1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.4 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. Specific hazards statements are given in Section 7.  
1.5 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.

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ASTM
ASTM C1165-23(Test Method)
Standard Test Method for Determining Plutonium by Controlled-Potential Coulometry in H2SO4 at a Platinum Working Electrode

SIGNIFICANCE AND USE
5.1 This test method is used to ascertain whether or not materials meet specifications for plutonium concentration or plutonium mass fraction.  
5.1.1 The materials (nuclear grade plutonium nitrate solutions, plutonium metal, plutonium oxide powder, and mixed oxide and carbide powders and pellets) to which this test method applies are subject to nuclear safeguards regulations governing their possession and use. However, adherence to this test method does not automatically guarantee regulatory acceptance of the resulting safeguards measurements. It remains the sole responsibility of the user of this test method to ensure that its application to safeguards has the approval of the proper regulatory authorities.  
5.1.2 When used in conjunction with appropriate certified reference materials (CRMs), this test method can demonstrate traceability to the international measurements system (SI).  
5.2 Fitness for Purpose of Safeguards and Nuclear Safety Application—Methods intended for use in safeguards and nuclear safety applications shall meet the requirements specified by Guide C1068 for use in such applications.  
5.3 A chemical calibration of the coulometer is necessary for accurate results.
FIG. 1 Example of a Cell Design Used at Los Alamos National Laboratory (LANL)
SCOPE
1.1 This test method covers the determination of milligram quantities of plutonium in unirradiated uranium-plutonium mixed oxide having a U/Pu ratio range of 0.1 to 10. This test method is also applicable to plutonium metal, plutonium oxide, uranium-plutonium mixed carbide, various plutonium compounds including fluoride and chloride salts, and plutonium solutions.  
1.2 The recommended amount of plutonium for each aliquant in the coulometric analysis is 5 mg to 10 mg. Precision worsens for lower amounts of plutonium, and elapsed time of electrolysis becomes impractical for higher amounts of plutonium.  
1.3 The quantity values stated in SI units are to be regarded as standard. The quantity values with non-SI units are given in parentheses for information only.  
1.4 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. Specific precautionary statements are given in Section 9.  
1.5 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.

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  • Standard
    6 pages
    English language
    sale 15% off