ASTM C 1233 : 2015
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
View Superseded by
Standard Practice for Determining Equivalent Boron Contents of Nuclear Materials
Hardcopy , PDF
11-11-2021
English
17-06-2015
Important note : All end users must be registered with an Account prior to user licenses being assigned.| Committee |
C 26
|
| DocumentType |
Standard Practice
|
| Pages |
3
|
| PublisherName |
American Society for Testing and Materials
|
| Status |
Superseded
|
| SupersededBy | |
| Supersedes |
1.1This 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 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.
1.2The 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.
1.3The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
| ASTM C 757 : 2016 : EDT 1 | Standard Specification for Nuclear-Grade Plutonium Dioxide Powder for Light Water Reactors |
| 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 |
| ASTM C 698 : 2016 | Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Mixed Oxides ((U, Pu)O<inf>2</inf>) |
| ASTM C 1065 : 2008 : R2015 | Standard Specification for Nuclear-Grade Zirconium Oxide Powder |
| 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 761 : 2018 | Standard Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Uranium Hexafluoride |
| 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 |
| 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 |
| ASTM C 785 : 2008 : R2015 | Standard Specification for Nuclear-Grade Aluminum Oxide Pellets |
| ASTM D 7219 : 2019 | Standard Specification for Isotropic and Near-isotropic Nuclear Graphites |
| ASTM C 781 : 2020 | Standard Practice for Testing Graphite Materials for Gas-Cooled Nuclear Reactor Components |
Access your standards online with a subscription
Features
-
Simple online access to standards, technical information and regulations.
-
Critical updates of standards and customisable alerts and notifications.
-
Multi-user online standards collection: secure, flexible and cost effective.