ASTM-C1233 › Historical Revision Information
Standard Practice for Determining Equivalent Boron Contents of Nuclear Materials
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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.
Keywords
boron; neutron absorption; nuclear materials; nuclear poisons; Boron content--nuclear-grade materials; Boron equivalents; EBC (equivalent boron contents); Neutron absorbing materials; Nuclear applications/materials; Nuclear poisons; ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)
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Document Number
ASTM-C1233-09
Revision Level
2009 EDITION
Status
Superseded
Modification Type
Revision
Publication Date
Aug. 1, 2009
Document Type
Practice
Page Count
3 pages
Committee Number
C26.02