1、Designation: C1233 15Standard Practice forDetermining Equivalent Boron Contents of NuclearMaterials1This standard is issued under the fixed designation C1233; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, the year of last revisio
2、n. A number in parentheses indicates the year of last reapproval. Asuperscript epsilon () indicates an editorial change since the last revision or reapproval.1. Scope1.1 This standard details a recommended practice for thecalculation of the Equivalent Boron Content (EBC) for nuclearmaterials. The EB
3、C is used to provide a measure of themacroscopic neutron absorption cross section of a nuclearmaterial. EBC factors for the natural elements are determinedfrom their atomic masses and thermal neutron absorption crosssections. This practice is illustrated by using EBC factors thatare based on thermal
4、 neutron (2200 m/s) absorption crosssections. Other EBC factors may be used depending upon theactual neutron energy spectrum.1.2 The EBC is a characteristic of a homogeneous material.Characterization of inhomogeneous materials and calculationof neutron multiplication factors require techniques that
5、arebeyond the scope of this practice.1.3 The values stated in SI units are to be regarded asstandard. No other units of measurement are included in thisstandard.2. Referenced Documents2.1 ASTM Standards:2C696 Test Methods for Chemical, Mass Spectrometric, andSpectrochemical Analysis of Nuclear-Grade
6、 Uranium Di-oxide Powders and PelletsC698 Test Methods for Chemical, Mass Spectrometric, andSpectrochemical Analysis of Nuclear-Grade Mixed Ox-ides (U, Pu)O2)C761 Test Methods for Chemical, Mass Spectrometric,Spectrochemical, Nuclear, and Radiochemical Analysis ofUranium HexafluorideC799 Test Method
7、s for Chemical, Mass Spectrometric,Spectrochemical, Nuclear, and Radiochemical Analysis ofNuclear-Grade Uranyl Nitrate SolutionsC859 Terminology Relating to Nuclear Materials3. Terminology3.1 Terminology used in this practice is in accordance withTerminology C859.4. Significance and Use4.1 Use of th
8、is standard practice yields an equivalent boroncontent (EBC) that can be used to characterize the neutron-absorbing properties of a nuclear material. The elementsincluded in the calculation are typically chosen so that the EBCrepresents either the entire material (for example, for a mod-erator) or t
9、he impurities in the material (for example, for anuclear fuel). This practice is typically used for materials inwhich thermal neutron absorption is undesirable. The EBC isnot intended for use as an input to any neutronic calculation.The EBC factors in Table 1 were selected to represent neutronabsorp
10、tion in water reactors under normal operating condi-tions. It is the responsibility of the user to evaluate theirsuitability for other purposes.5. Procedures for EBC Determination5.1 Agreement shall be reached between the buyer andseller as to which elements shall be analyzed for calculation oftheir
11、 EBC. It is recommended that B, Cd, Dy, Eu, Sm, and Gdbe included in this calculation. Analytical methods for suchelements shall be those given in Test Methods C696, C698,C761, and C799 as applicable or as otherwise agreed uponbetween buyer and seller.5.2 The individual EBC values are calculated usi
12、ng the EBCfactors from Table 1 as follows:EBC of constituent =(EBC factor of constituent)(g of constituent/gofmaterial)where:EBC factor of constituent = (atomic mass of boron)(aofconstituent)/(atomic mass of constituent)(a of boron), anda = atomic neutron absorption cross section in barns.The EBC fa
13、ctors have been calculated using a value of 764barns for the neutron absorption cross section (a) of boron.This value may vary in nature according to the isotopic1This practice is under the jurisdiction of ASTM Committee C26 on NuclearFuel Cycle and is the direct responsibility of Subcommittee C26.0
14、2 on Fuel andFertile Material Specifications.Current edition approved June 1, 2015. Published June 2015. Originallyapproved in 1993. Last previous approved in 2009 as C1233 09. DOI: 10.1520/C1233-15.2For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service
15、 at serviceastm.org. For Annual Book of ASTMStandards volume information, refer to the standards Document Summary page onthe ASTM website.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States1TABLE 1 Equivalent Boron Content FactorsElementN
16、eutron Absorption Cross SectionA(Barns) at2200 m/sAtomic MassBEBC FactorAluminiumC0.231 26.98 1.21E-04Antimony 5.1D121.75 5.93E-04Argon 0.68 39.95 2.41E-04Arsenic 4.5 74.92 8.50E-04BariumC1.2D137.33 1.24E-04BerylliumC0.0076D9.01 1.19E-05BismuthC0.0338 208.98 2.29E-06Boron 764E10.81 1.00E+00Bromine 6
17、.9 79.91 1.22E-03Cadmium 2520 112.41 3.17E-01CalciumC0.43 40.08 1.52E-04CarbonC0.0035 12.01 4.12E-06CeriumC0.63D140.12 6.36E-05Cesium 29 132.91 3.09E-03Chlorine 33.5 35.45 1.34E-02Chromium 3.07 52.00 8.35E-04Cobalt 37.2 58.93 8.93E-03Copper 3.78 63.54 8.42E-04Dysprosium 940 162.50 8.18E-02Erbium 159
18、.2 167.26 1.35E-02Europium 4565 151.97 4.25E-01FluorineC0.0096D19.00 7.15E-06Gadolinium 48890 157.25 4.40E+00Gallium 2.9 69.72 5.89E-04Germanium 2.3D72.59 4.48E-04Gold 98.65 196.97 7.09E-03Hafnium 104.1 178.49 8.25E-03HeliumC0.0073 4.00 2.58E-05Holmium 64.7 164.93 5.55E-03Hydrogen 0.33 1.01 4.62E-03
19、Indium 193.8D114.82 2.39E-02Iodine 6.2 126.90 6.91E-04Iridium 425.30 192.22 3.13E-02Iron 2.56D55.85 6.49E-04Krypton 25.00 83.80 4.22E-03Lanthanum 8.97D138.91 9.14E-04LeadC0.171 207.2 1.17E-05Lithium 70.6F6.94 1.44E-01Lutetium 76.4 174.97 6.18E-03MagnesiumC0.063 24.31 3.67E-05Manganese 13.3 54.94 3.4
20、3E-03Mercury 372.3 200.59 2.63E-02Molybdenum 2.55D95.94 3.76E-04Neodymium 50.5D144.24 4.95E-03NeonC0.039 20.18 2.73E-05Nickel 4.49D58.69 1.08E-03NiobiumC1.15 92.91 1.75E-04Nitrogen 1.90 14.01 1.92E-03Osmium 16.00 190.20 1.19E-03OxygenC0.00019D16.00 1.68E-07Palladium 6.90 106.42 9.17E-04PhosphorusC0.
21、172 30.97 7.86E-05Platinum 10.30 195.08 7.47E-04Potassium 2.1D39.10 7.60E-04Praseodymium 11.5 140.91 1.15E-03Rhenium 89.70 186.21 6.82E-03Rhodium 145.20 102.91 2.00E-02RubidiumC0.38D85.47 6.29E-05Ruthenium 2.56D101.07 3.58E-04Samarium 5670 150.36 5.34E-01Scandium 27.20 44.96 8.56E-03Selenium 11.70 7
22、8.96 2.10E-03SiliconC0.171 28.09 8.61E-05Silver 63.3 107.87 8.30E-03Sodium 0.53 22.99 3.26E-04Strontium 1.28D87.62 2.07E-04Sulfur 0.52 32.06 2.29E-04Tantalum 20.6 180.95 1.61E-03Tellurium 4.70 127.60 5.21E-04Terbium 23.4 158.92 2.08E-03Thallium 3.43 204.37 2.37E-04Thorium 7.37 232.04 4.49E-04Thulium
23、 105 168.93 8.79E-03TinC0.626D118.71 7.46E-05C1233 152composition of the elements. If an alternative value is chosenthe EBC factors must be recalculated using the chosen value.5.3 If the concentration of any of the elements used in thecalculation is reported as a “less than” value, that value shall
24、beused in calculating the EBC.5.4 A total EBC value, if required, is determined by thesummation of individual EBC values.5.5 Plutonium and uranium have not been included, as theyare fissionable elements.5.6 Table 1 includes elements that may provide a negligiblecontribution to the total EBC. In part
25、icular, elements with bothsmall concentrations and very small EBC factors (less than2E-4) will generally provide a negligible contribution to theEBC of the material as a whole. Such elements should beexcluded from determinations of the total EBC.6. Keywords6.1 boron; neutron absorption; nuclear mate
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31、 http:/ 1 ContinuedElementNeutron Absorption Cross SectionA(Barns) at2200 m/sAtomic MassBEBC FactorTitanium 6.1 47.88 1.80E-03Tungsten 18.4 183.85 1.42E-03Vanadium 5.08 50.94 1.41E-03Xenon 23.90 131.29 2.58E-03Ytterbium 35.5 173.04 2.90E-03Yttrium 1.28 88.91 2.04E-04Zinc 1.11 65.39 2.40E-04Zirconium
32、C0.185D91.22 2.87E-05ANeutron Cross Sections, Vol 1, Parts A and B, Academic Press, New York, 1981 and 1984, respectively.BHolden, N. E., and Martin, R. L., Pure and Applied Chemistry, Vol 56, p. 653, 1984.CWhen present in small concentrations, this element should be excluded from determinations of
33、the total EBC.DIn the absence of other data, the neutron capture cross section for a Maxwellian flux is used.ECross section is primarily due to a single isotope, whose isotopic abundance is variable in nature. The value can vary between 733 and 779 barns depending upon thesource. See Holden, N. E.,
34、Neutron Capture Cross Section Standards for BNL-325, Fourth Ed., BNL-NCS-51388, January 1981.FCross section is primarily due to a single isotope, whose isotopic abundance is variable in nature. The value can vary between 69 and 72 barns depending upon thesource. See Holden, N. E., Neutron Capture Cross Section Standards for BNL-325, Fourth Ed., BNL-NCS-51388, January 1981.C1233 153
