Active Standard ASTM C788 | Developed by Subcommittee: C26.02
Book of Standards Volume: 12.01
Historical (view previous versions of standard)
This specification applies to nuclear-grade aqueous uranyl nitrate solution or crystals not exceeding 5% 235U intended for subsequent manufacture into either UF6 or direct conversion to uranium oxide. This specification is intended to provide the nuclear industry with a general standard for aqueous uranyl nitrate solution or crystals. The purpose of this specification is: to define the impurity and uranium isotope limits for commercial standard uranyl nitrate, and to define additional limits for reprocessed uranyl nitrate (or any mixture of reprocessed and commercial standard uranyl nitrate).
This abstract is a brief summary of the referenced standard. It is informational only and not an official part of the standard; the full text of the standard itself must be referred to for its use and application. ASTM does not give any warranty express or implied or make any representation that the contents of this abstract are accurate, complete or up to date.
1.1 This specification applies to nuclear-grade aqueous uranyl nitrate solution or crystals not exceeding 5 % 235U intended for subsequent manufacture into either UF6 (for feed to an enrichment plant) or direct conversion to uranium oxide (for use in reactors).
1.2 This specification is intended to provide the nuclear industry with a general standard for aqueous uranyl nitrate solution or crystals. It recognizes the diversity of manufacturing methods and the processes to which it is subsequently to be subjected. It is therefore anticipated that it may be necessary to include supplementary specification limits by agreement between purchaser and manufacturer. Different limits are appropriate depending on whether or not the uranyl nitrate is to be converted to UF6 for subsequent processing.
1.3 The purpose of this specification is: (a) to define the impurity and uranium isotope limits for commercial standard uranyl nitrate, and (b) to define additional limits for reprocessed uranyl nitrate (or any mixture of reprocessed and commercial standard uranyl nitrate). For such uranyl nitrates, special provisions may need to be made to ensure that no extra hazard arises to the employees, the process equipment, or the environment.
1.4 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents, for health and safety, or for shipping. Observance of this standard does not relieve the user of the obligation to conform to all international, federal, state and local regulations for processing, shipping, or any other way of using the uranyl nitrate. An example of a U.S. Government Document is the Code of Federal Regulations, Title 10, Part 50 (latest edition).
1.5 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
1.6 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 and health practices and determine the applicability of regulatory limitations prior to use.
2. Referenced Documents (purchase separately) The documents listed below are referenced within the subject standard but are not provided as part of the standard.
C787 Specification for Uranium Hexafluoride for Enrichment
C799 Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Nuclear-Grade Uranyl Nitrate Solutions
C859 Terminology Relating to Nuclear Materials
C996 Specification for Uranium Hexafluoride Enriched to Less Than 5 % 235U
C1233 Practice for Determining Equivalent Boron Contents of Nuclear Materials
C1295 Test Method for Gamma Energy Emission from Fission Products in Uranium Hexafluoride and Uranyl Nitrate Solution
ANSI StandardANSI/ASMENQA-1 Quality Assurance, Requirements for Nuclear Facility Applications
U.S. Government DocumentCodeofFederalRegulat (Energy), Part 50, Domestic Licensing of Production and Utilization Facilities
ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)
UNSPSC Code 15131500(Nuclear fuel)