Standard Test Method for the Determination of Uranium by Ignition and the Oxygen to Uranium (O/U) Atomic Ratio of Nuclear Grade Uranium Dioxide Powders and Pellets

SIGNIFICANCE AND USE
The test method is designed to show whether or not a material meets the specifications as given in Specifications C 753 or C 776.
The powder’stoichiometry is useful for predicting the oxide’sintering behavior in the pellet production process.
SCOPE
1.1 This test method covers the determination of uranium and the oxygen to uranium atomic ratio in nuclear grade uranium dioxide powder and pellets.
1.2 This test method does not include provisions for preventing criticality accidents or requirements for health and safety. Observance of this test method does not relieve the user of the obligation to be aware of and conform to all international, national, or federal, state and local regulations pertaining to possessing, shipping, processing, or using source or special nuclear material.
1.3 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.
1.4 This test method also is applicable to UO3 and U3O8 powder.

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Status
Historical
Publication Date
30-Jun-2011
Technical Committee
Drafting Committee
Current Stage
Ref Project

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ASTM C1453-00(2011) - Standard Test Method for the Determination of Uranium by Ignition and the Oxygen to Uranium (O/U) Atomic Ratio of Nuclear Grade Uranium Dioxide Powders and Pellets
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NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.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: C1453 − 00 (Reapproved 2011)
Standard Test Method for
the Determination of Uranium by Ignition and the Oxygen to
Uranium (O/U) Atomic Ratio of Nuclear Grade Uranium
Dioxide Powders and Pellets
This standard is issued under the fixed designation C1453; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision.Anumber in parentheses indicates the year of last reapproval.A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope C1287Test Method for Determination of Impurities in
Nuclear Grade Uranium Compounds by Inductively
1.1 This test method covers the determination of uranium
Coupled Plasma Mass Spectrometry
and the oxygen to uranium atomic ratio in nuclear grade
uranium dioxide powder and pellets.
3. Summary of Test Method
1.2 This test method does not include provisions for pre-
3.1 A weighed portion of UO is converted to U O by
2 3 8
venting criticality accidents or requirements for health and
repeated ignition at 900°C in air, to a constant weight.
safety.Observanceofthistestmethoddoesnotrelievetheuser
Corrections are made for nonvolatile and volatile impurities
of the obligation to be aware of and conform to all
including moisture, based on independent determinations de-
international, national, or federal, state and local regulations 3,4
scribed in Test Methods C696 and C1287.
pertaining to possessing, shipping, processing, or using source
or special nuclear material.
4. Significance and Use
1.3 This standard does not purport to address all of the
4.1 The test method is designed to show whether or not a
safety concerns, if any, associated with its use. It is the
material meets the specifications as given in Specifications
responsibility of the user of this standard to establish appro-
C753 or C776.
priate safety and health practices and determine the applica-
4.2 The powder’s stoichiometry is useful for predicting the
bility of regulatory limitations prior to use.
oxide’s sintering behavior in the pellet production process.
1.4 This test method also is applicable to UO and U O
3 3 8
powder.
5. Interferences
5.1 The moisture content must be determined and a correc-
2. Referenced Documents
tion must be made for the moisture content otherwise a high
2.1 ASTM Standards:
bias will occur for the O/U ratio.
C696Test Methods for Chemical, Mass Spectrometric, and
5.2 A nonvolatile impurity correction must be made other-
SpectrochemicalAnalysis of Nuclear-Grade Uranium Di-
wiseahighbiaswilloccurfortheuraniumvalue.Anextended
oxide Powders and Pellets
ignition time may be required if significant amounts of anions
C753Specification for Nuclear-Grade, Sinterable Uranium
that are difficult to decompose are present.
Dioxide Powder
C776Specification for Sintered Uranium Dioxide Pellets
5.3 TheU O touraniumconversionfactorandtheuranium
3 8
C1267Test Method for Uranium by Iron (II) Reduction in
atomic weight will require adjustment for nonnatural isotopic
PhosphoricAcid Followed by Chromium (VI)Titration in
concentrations otherwise a bias will be present.
the Presence of Vanadium
6. Apparatus
6.1 Desiccator, containing a moisture absorbent.
This test method is under the jurisdiction ofASTM committee C26 on Nuclear
6.2 Muffle Furnace, capable of maintaining and controlling
Fuel Cycle and is the direct responsibility of Subcommittee C26.05 on Methods of
temperatures to 900 6 25°C.
Test.
CurrenteditionapprovedJuly1,2011.PublishedJuly2011.Originallyapproved
in 2000. Last previous edition approved in 2006 as C1453–00R06. DOI: 10.1520/
C1453-00R11. Jones, R.J., Ed., “Selected Measurement Methods for Plutonium and Uranium
For referenced ASTM standards, visit the ASTM website, www.astm.org, or in the Nuclear Fuel Cycle,” USAEC Document TID-7029, 1963, AERDB, pp.
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM 91–93.
Standards volume information, refer to the standard’s Document Summary page on Petit, G.D. and Keinberger, C.A., “Preparation of Stoichiometric U O ,”
3 8
the ASTM website. Analytical Chemistry, ANCHA, Vol 25, 1961, p. 579.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
C1453 − 00 (2011)
TABLE 1 Oxide Conversion Factors for Impurity Correction
9. Calculation
A
Impurity Assumed Oxide Form Oxide Conversion Factor
9.1 Uranium Content—Calculate as follows:
Al Al O 1.89
2 3
U, wt% 5 @ 0.8480 W 2WI /S X 100# 2C (1)
BB O 3.23 ~ ~ ! !
2 3
Ba BaO 1.12
where:
Be BeO 2.78
Bi Bi O 1.11
2 3
0.8480 = U O to uranium conversion factor for natural
3 8
Ca CaO 1.40
uranium. This factor will require adjustment when
Cd CdO 1.14
Co Co O 1.41
the uranium isotopic abundance deviates from
2 3
Cr Cr O 1.46
2 3
natural uranium. See Appendix X1.2.
Cu CuO 1.25
W = Grams of U O after ignition.
Fe Fe O 1.43 3 8
2 3
B
I = Total of all detected nonvolatile impurities ex-
In In O 1.21
2 3
Li Li O 2.15
pressed as grams of oxide per gram of ignited
Mg MgO 1.66
U O . See Table 1 to obtain oxide conversion
Mn MnO 1.58 3 8
Mo MoO 1.50 factors for many common impurity elements en-
Na Na O 1.35
countered. The impurities are determined as de-
Ni NiO 1.27
scribed in either Test Method C696 or C1287.
PP O 2.29
2 5
S = Initial sample weight, in g.
Pb PbO 1.15
Sb Sb O 1.26
2 4 C = Total of all nonvolatile impurities analyzed as less
Si SiO 2.14
than the lower detection limit of the analytical
Sn SnO 1.27
method. The detection limit values shall be taken
Ti TiO 1.67
VV O 1.79
2 5
as the concentration of that element. The total is
Zn ZnO 1.24
expressed as percent. These impurities are deter-
Zr ZrO 1.35
minedasdescribedinTestMethodC696orC1287.
Ta Ta O 1.22
2 5
WWO 1.26
3 Alternatively, the these impurities can be consid-
A
Oxide conversion factor is defined as grams oxide per gram of element.
ered to contribute a total correction of 0.01% to
B
This element is not required by the UO Specifications C753 and C776 but is
the uranium percent.
included for information only.
9.2 Oxygen-to-Uranium Ratio—Calculate as follows from
...

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