ASTM C1348-01

Standard Specification for Blended Uranium Oxides with a ²³⁵U Content of Less Than 5 % for Direct Hydrogen Reduction to Nuclear Grade Uranium Dioxide

SCOPE
1.1 This specification covers blended uranium trioxide (UO3), U3O8, or mixtures of the two, powders that are intended for conversion into a sinterable uranium dioxide (UO2) powder by means of a direction reduction process. The UO2 powder product of the reduction process must meet the requirements of Specification C753 and be suitable for subsequent UO2 pellet fabrication by pressing and sintering methods. This specification applies to uranium oxides with a 235U enrichment less than 5 %.
1.2 This specification includes chemical, physical, and test method requirements for uranium oxide powders as they relate to the suitability of the powder for storage, transportation, and direct reduction of UO2 powder. This specification is applicable to uranium oxide powders for such use from any source.
1.3 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 specification does not relieve the user of the obligation to conform to all international, national, state, and local regulations for processing, shipping, or any other way of using uranium oxide powders (see 2.2 and 2.3).
1.4 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.
1.5 The following safety hazards caveat pertains only to the test methods portion of the annexes in this specification: 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.

General Information

• Status: Historical
• Publication Date: 09-Jan-2001
• ICS: 27.120.30 - Fissile materials and nuclear fuel technology
• Technical Committee: C26 - Nuclear Fuel Cycle
• Drafting Committee: C26.02 - Fuel and Fertile Material Specifications

Relations

• Replaces: ASTM C1348-96 - Standard Specification for Blended Uranium Oxides with a ²³⁵U Content of Less Than 5 % for Direct Hydrogen Reduction to Nuclear Grade Uranium Dioxide
• Effective Date: 10-Jan-2001
• Replaced By: ASTM C1348-01(2008) - Standard Specification for Blended Uranium Oxides with ²³⁵U Content of Less Than 5 % for Direct Hydrogen Reduction to Nuclear Grade Uranium Dioxide (Withdrawn 2013)
• Effective Date: 01-Jun-2008
• Referred By: ASTM C1413-18 - Standard Test Method for Isotopic Analysis of Hydrolyzed Uranium Hexafluoride and Uranyl Nitrate Solutions by Thermal Ionization Mass Spectrometry
• Effective Date: 10-Jan-2001

Standards Content (Sample)

NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Contact ASTM International (www.astm.org) for the latest information
Designation: C 1348 – 01
Standard Specification for
235
Blended Uranium Oxides with a U Content of Less Than
5 % for Direct Hydrogen Reduction to Nuclear Grade
1
Uranium Dioxide
This standard is issued under the fixed designation C 1348; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (e) indicates an editorial change since the last revision or reapproval.
INTRODUCTION
This specification is intended to provide the nuclear industry with a general standard for such
uranium oxide powders. It recognizes the diversity of conversion processes and the many special
requirements for chemical and physical characterization that may be imposed by the end use of the
powder. It is anticipated, therefore, that this specification may be supplemented with additional
requirements by agreement between the buyer and the seller.
1. Scope if any, associated with its use. It is the responsibility of the user
of this standard to establish appropriate safety and health
1.1 This specification covers blended uranium trioxide
practices and determine the applicability of regulatory limita-
(UO ),U O ,ormixturesofthetwo,powdersthatareintended
3 3 8
tions prior to use.
for conversion into a sinterable uranium dioxide (UO ) powder
2
by means of a direct reduction process. The UO powder
2
2. Referenced Documents
product of the reduction process must meet the requirements of
2.1 ASTM Standards:
Specification C 753 and be suitable for subsequent UO pellet
2
B 329 Test Method forApparent Density of Metal Powders
fabrication by pressing and sintering methods. This specifica-
2
235
and Related Compounds Using the Scott Volumeter
tionappliestouraniumoxideswitha Uenrichmentlessthan
C 696 Test Methods for Chemical, Mass Spectrometric, and
5%.
Spectrochemical Analysis of Nuclear-Grade Uranium Di-
1.2 This specification includes chemical, physical, and test
3
oxide Powders and Pellets
method requirements for uranium oxide powders as they relate
C 753 Specification for Nuclear-Grade, Sinterable Uranium
to the suitability of the powder for storage, transportation, and
3
Dioxide Powder
directreductiontoUO powder.Thisspecificationisapplicable
2
C 799 Test Methods for Chemical, Mass Spectrometric,
to uranium oxide powders for such use from any source.
Spectrochemical, Nuclear, and Radiochemical Analysis of
1.3 The scope of this specification does not comprehen-
3
Nuclear-Grade Uranyl Nitrate Solutions
sively cover all provisions for preventing criticality accidents,
3
C 859 Terminology Relating to Nuclear Materials
for health and safety, or for shipping. Observance of this
C 996 Specification for Uranium Hexafluoride Enriched to
specification does not relieve the user of the obligation to
235 3
Less Than 5 % U
conform to all international, national, state, and local regula-
C 1233 Practice for Determining Equivalent Boron Con-
tions for processing, shipping, or any other way of using
3
tents of Nuclear Materials
uranium oxide powders (see 2.2 and 2.3).
C 1287 Test Method for Determination of Impurities in
1.4 The values stated in SI units are to be regarded as the
Uranium Dioxide by Inductively Coupled Plasma Mass
standard. The values given in parentheses are for information
3
Spectrometry
only.
E 11 Specification for Wire-Cloth Sieves for Testing Pur-
1.5 The following safety hazards caveat pertains only to the
4
poses
test methods portion of the annexes in this specification: This
4
E 105 Practice for Probability Sampling of Materials
standard does not purport to address all of the safety concerns,
1
This specification is under the jurisdiction of ASTM Committee C26 on
Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fuel
2
and Fertile Material Specifications. Annual Book of ASTM Standards, Vol 02.05.
3
Current edition approved Jan. 10, 2001. Published March 2001. Originally Annual Book of ASTM Standards, Vol 12.01.
4
published as C 1348–96. Last previous edition C 1348–96. Annual Book of ASTM Standards, Vol 14.02.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
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C 1348
TABLE 1 Impurity Elements and Maximum Concentration Limits
2.2 ANSI Standard:
NQA-1 Quality Assurance Program, Requirements for Maximum Concentration Limit of Uranium,
Element
5 µg/gU
Nuclear Facilities
Aluminum 50
2.3 U.S. Government Document:
Barium 5
CFR Title 10 (Energy), Part 50, Domestic Licensing of
Beryllium 100
6
Production and Utilization Facilities
Bismuth 3
Calcium + magnesium 100
Carbon 100
3. Terminology
Chlorine 100
3.1 Definitions—Terms shall be defined in accordance with Chromium 100
Cobalt 80
Ter
...