ASTM C 1233 : 2003
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
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Standard Practice for Determining Equivalent Boron Contents of Nuclear Materials
Hardcopy , PDF
11-11-2014
English
10-07-2003
Important note : Users cannot be edited or removed once added to your Multi user PDF.| Committee |
C 26
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| DocumentType |
Standard Practice
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| Pages |
3
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| PublisherName |
American Society for Testing and Materials
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| Status |
Superseded
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| SupersededBy | |
| Supersedes |
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.| ASTM C 785 : 2008 : R2015 | Standard Specification for Nuclear-Grade Aluminum Oxide Pellets |
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| ASTM C 833 : 2017 | Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pellets for Light Water Reactors |
| ASTM C 1783 : 2015 | Standard Guide for Development of Specifications for Fiber Reinforced Carbon-Carbon Composite Structures for Nuclear Applications |
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| ASTM C 799 : 2019 | Standard Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Nuclear-Grade Uranyl Nitrate Solutions |
| ASTM C 753 : 2016 : REV A | Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder |
| ASTM C 776 : 2017 | Standard Specification for Sintered Uranium Dioxide Pellets for Light Water Reactors |
| ASTM C 1334 : 2005 : R2016 : EDT 1 | Standard Specification for Uranium Oxides with a <sup>235</sup>U Content of Less Than 5 % for Dissolution Prior to Conversion to Nuclear-Grade Uranium Dioxide |
| ASTM C 781 : 2018 | Standard Practice for Testing Graphite Materials for Gas-Cooled Nuclear Reactor Components |
| ASTM D 7219 : 2008 : R2014 | Standard Specification for Isotropic and Near-isotropic Nuclear Graphites |
| ASTM C 1462 : 2000 : R2013 | Standard Specification for Uranium Metal Enriched to More than 15 % and Less Than 20 % 235U |
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| ASTM D 7301 : 2011 : R2015 | Standard Specification for Nuclear Graphite Suitable for Components Subjected to Low Neutron Irradiation Dose |
| ASTM C 697 : 2016 | Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Plutonium Dioxide Powders and Pellets |
| ASTM C 708 : 2016 | Standard Specification for Nuclear-Grade Beryllium Oxide Powder (Withdrawn 2024) |
| ASTM C 788 : 2003 : R2015 | Standard Specification for Nuclear-Grade Uranyl Nitrate Solution or Crystals |
| ASTM C 1793 : 2015 | Standard Guide for Development of Specifications for Fiber Reinforced Silicon Carbide-Silicon Carbide Composite Structures for Nuclear Applications |
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