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

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

• Replaced By: 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
• 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NOTICE: This standard has either been superseded and replaced by a new version or
withdrawn.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 – 96
AMERICAN SOCIETY FOR TESTING AND MATERIALS
100 Barr Harbor Dr., West Conshohocken, PA 19428
Reprinted from the Annual Book of ASTM Standards. Copyright ASTM
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 practices and determine the applicability of regulatory limita-
tions prior to use.
1.1 This specification covers blended uranium trioxide
(UO ), U O , or mixtures of the two, powders that are intended
3 3 8
2. Referenced Documents
for conversion into a sinterable uranium dioxide (UO ) powder
2
2.1 ASTM Standards:
by means of a direct reduction process. The UO powder
2
B 329 Test Method for Apparent Density of Metal Powders
product of the reduction process must meet the requirements of
2
and Related Compounds Using the Scott Volumeter
Specification C 753 and be suitable for subsequent UO pellet
2
C 696 Test Methods for Chemical, Mass Spectrometric, and
fabrication by pressing and sintering methods. This specifica-
235
Spectrochemical Analysis of Nuclear-Grade Uranium Di-
tion applies to uranium oxides with a U enrichment less than
3
oxide Powders and Pellets
5%.
C 753 Specification for Nuclear-Grade, Sinterable Uranium
1.2 This specification includes chemical, physical, and test
3
Dioxide Powder
method requirements for uranium oxide powders as they relate
C 799 Test Methods for Chemical, Mass Spectrometric,
to the suitability of the powder for storage, transportation, and
Spectrochemical, Nuclear, and Radiochemical Analysis of
direct reduction to UO powder. This specification is applicable
2
3
Nuclear-Grade Uranyl Nitrate Solutions
to uranium oxide powders for such use from any source.
3
C 859 Terminology Relating to Nuclear Materials
1.3 The scope of this specification does not comprehen-
C 996 Specification for Uranium Hexafluoride Enriched to
sively cover all provisions for preventing criticality accidents,
235
3
Less Than 5 % U
for health and safety, or for shipping. Observance of this
C 1233 Practice for Determining Equivalent Boron Con-
specification does not relieve the user of the obligation to
3
tents of Nuclear Materials
conform to all international, national, state, and local regula-
C 1287 Test Method for Determination of Impurities in
tions for processing, shipping, or any other way of using
Uranium Dioxide by Inductively Coupled Plasma Mass
uranium oxide powders (see 2.2 and 2.3).
3
Spectrometry
1.4 The values stated in SI units are to be regarded as the
E 11 Specification for Wire-Cloth Sieves for Testing Pur-
standard. The values given in parentheses are for information
4
poses
only.
4
E 105 Practice for Probability Sampling of Materials
1.5 The following safety hazards caveat pertains only to the
2.2 ANSI Standard:
test methods portion of the annexes in this specification: This
NQA-1 Quality Assurance Program, Requirements for
standard does not purport to address all of the safety concerns,
5
Nuclear Facilities
if any, associated with its use. It is the responsibility of the user
of this standard to establish appropriate safety and health
2
Annual Book of ASTM Standards, Vol 02.05.
1 3
This specification is under the jurisdiction of ASTM Committee C-26 on Annual Book of ASTM Standards, Vol 12.01.
4
Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fuel Annual Book of ASTM Standards, Vol 14.02.
5
and Fertile Material Specifications. Available from American National Standards Institute, 11 W. 42nd St., 13th
Current edition approved July 10, 1996. Published September 1996. Floor, New York, NY 10036.
1

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C 1348
TABLE 1 Impurity Elements and Maximum Concentration Limits
2.3 U.S. Government Document:
CFR Title 10 (Energy), Part 50, Domestic Licensing of Maximum Concentration Limit of Uranium,
Element
6 μg/gU
Production and Utilization Facilities
Aluminum 50
3. Terminology Barium 5
Beryllium 100
3.1 Definitions—Terms shall be
...