Designation: C 1380 – 97
Standard Test Method for
the Determination of Uranium Content and Isotopic
Composition by Isotope Dilution Mass Spectrometry1
This standard is issued under the fixed designation C 1380; 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.
1. Scope
1.1 This test method covers a method for the determination
of the uranium concentration in uranium oxides by isotope
dilution mass spectrometry (IDMS). The isotopic composition
of the oxide is measure simultaneously.
1.2 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 appro-
priate safety and health practices and determine the applica-
bility of regulatory limitations prior to use.
2. Referenced Documents
2.1 ASTM Standards:
D 1193 Specification for Reagent Water2
3. Summary of Test Method
3.1 For measurement of the elemental uranium concentra-
tion of uranium oxides by IDMS, a representative and accu-
rately measured aliquot of the sample is prepared. A known
quantity of 233U (“spike”) is added to an aliquot of the sample.
The sample aliquot and spike are taken to dryness, redissolved
in dilute nitric acid, and loaded on a filament for analysis in a
thermal ionization mass spectrometer (TIMS). After measure-
ment of the isotopic ratios in the spiked sample, the uranium
content and isotopic composition of sample are calculated.
4. Significance and Use
4.1 Determination of percent uranium content and 235U
abundance in oxides and other materials containing high
concentrations of uranium is required for special nuclear
materials accountability, regulatory requirements, and process
control.
5. Interferences
5.1 The calculations assume any 233U in the sample is
negligible. If the sample contains significant 233U, the sample
must be analyzed for isotopic composition with and without
added spike, and the calculations adjusted accordingly.
6. Apparatus
6.1 Thermal ionization mass spectrometer (TIMS) config-
ured with Faraday cup detectors and an automated operating
system.
6.2 Preconditioning unit for the TIMS.
6.3 Filament loading assembly for the TIMS.
6.4 Balance, analytical, with five-place range.
6.5 Vials, glass, disposable with plastic caps.
6.6 Pipet, automatic, Ranin or equivalent, variable to 1000
µL.
6.7 Pipet tips, disposable plastic, 100–1000 µL.
6.8 Liquid dispenser, Repipettey or equivalent.
7. Reagents and Materials
7.1 Purity of Materials—Reagent grade chemicals shall be
used in all tests. Unless otherwise indicated, it is intended that
all reagents conform to the specification of the Committee on
Analytical Reagents of the American Chemical Society where
such specifications are available.3 Other grades may be used
provided it is first ascertained that the reagent is of sufficiently
high purity to permit its use without lessening the accuracy of
the determination.
7.2 Purity of Water—Unless otherwise indicated, references
to water shall mean reagent water in conformance with
Specification D 1193.
7.3 Nitric Acid, HNO3, concentrated (70 %).
7.4 Nitric Acid, 0.8 M (5 % v/v)—Cautiously add 50 mL of
concentrated nitric acid to 950 mL of water.
7.5 Nitric Acid, 0.1 M—Add 6.5 mL concentrated nitric acid
to ’900 mL of water, mix, and bring to 1000 mL with water.
7.6 Hydrogen Peroxide H2O2, 30 %.
7.7 Elemental and Isotopic Uranium Standards (New Brun-
swick Laboratory CRM 114, CRM 116 CRM 129, or equiva-
lent4).
7.8 Uranium-233 spike assay and isotopic standard (NBL
CRM 111–A4 or equivalent)—Dilute NBL CRM 111–A 1:50
1 This test method is under the jurisdiction of ASTM Committee C-26 on Nuclear
Fuel Cycle and is the direct responsibility of Subcommittee C26.05 on Methods of
Test.
Current edition approved December 10, 1997. Published May 1998.
2 Annual Book of ASTM Standards, Vol 11.01.
3 Reagent Chemicals, American Chemical Society Specifications, American
Chemical Society, Washington, D. C. For suggestions on the testing of reagents not
listed by the American Chemical Society, Washington, D. C. For suggestions on the
testing of reagents not listed by the American Chemical Society, see Analar
Standards for Laboratory Chemicals, BDH Ltd., Poole, Dorset, U. K., and the
United States Pharmacopeia and National Formulary, U.S. Pharmaceutical Con-
vention (USPC), Rockville, MD.
4 Available from the US Department of Energy, New Brunswick Laboratory, D
350, 9800 South Cass Avenue, Argonne, IL 60439.
1
Copyright © ASTM, 100 Barr Harbor Drive, West Conshohocken, PA 19428-2959, United States.
by weight with a 5 % nitric acid to give a 233U concentration of
approximately 10 µg 233U/g solution.
NOTE 1—An exact 1:50 dilution is not required. The requirement is for
precise and accurate weights of standard and diluent. Calculate the exact
concentration of each isotope in the diluted spike standard in accordance
with 11.2. Other dilutions of CRM-111A may be used if accurate weights
are known, and the aliquot of CRM 111–A used in the measurement of test
samples yields a 233U/23XU ratio of at least 0.02, where X is the major
uranium isotope.
8. Preparation of Apparatus
8.1 Prepare the thermal ionization mass spectrometer
(TIMS) in accordance with manufacturer’s recommendations.
9. Calibration and Standardization
9.1 Standardization of 233U Spike Solution:
9.1.1 Prior to using a new diluted spike solution, verify the
concentration of the solution with CRM 129 uranium oxide or
its equivalent. If the new spike solution does not give results
within control limits, its standardized concentration must be
verified with another NBL certified reference material for
elemental uranium, such as CRM 114 or equivalent.
9.2 Calibration of TIMS:
9.2.1 Calibrate the TIMS in accordance with manufacturer’s
recommendations to achieve the user’s performance and qual-
ity assurance criteria.
10. Procedure
10.1 Weigh, to the nearest 0.01 mg, a labeled vial and cap
for each sample; record the weight.
10.2 Tare the balance and weight, to the nearest 0.01 mg, a
0.35–0.45 g aliquot of the sample into the vial. Record the
weight.
NOTE 2—Smaller or larger aliquots of sample may be used. However,
the sample size should be sufficient to obtain a representative sample of
the material and the ratio of the measured 233U to major uranium isotope
in the material must be greater than 0.02. It is recommended that samples
be prepared in duplicate.
10.3 Cautiously add 5 mL concentrated HNO3 to the sample
and heat slowly on a hot plate to dissolve the sample.
10.4 Heat the sample/HNO3 to dryness.
10.5 Remove the sample from the hot plate and examine the
residue.
NOTE 3—If conversion of the sample to orange/red uranium nitrate/
oxide was incomplete, repeat Steps 10.3-10.5.
10.6 After conversion is complete and the sample is dry,
cool the vial, add 40 mL 0.8 M HNO3, and cap with the
appropriate plastic lined cap.
10.7 Mix the vial contents thoroughly by inverting vigor-
ously.
10.8 Weigh the vial and its contents to the nearest 0.1 mg
and record the weight.
10.9 Label a new 20–mL vial with sample identification
number and “Dil 1.”
10.10 Place the labeled vial and a plastic lined cap on the
balance, and zero the balance.
10.11 Add 0.5 mL of the original dilution (from step 10.8),
set the cap on the vial, and record the weight to the nearest 0.01
mg.
10.12 Tare the balance, add 20 mL of 0.8 M HNO3, and
record the weight to the nearest 0.01 mg.
10.13 Cap the vial and mix the contents thoroughly by
inverting vigorously.
10.14 Label a third vial with sample identification and “Dil
2,” place the vial and a plastic lined cap on the balance, and
zero the balance.
10.15 Add 0.5 mL of Dilution 1, set the cap on the vial, and
record the weight to the nearest 0.01 mg.
10.16 Tare the balance, add 0.5 mL of 233U spike solution to
the vial, and record the weight to the nearest 0.01 mg.
10.17 Add five drops of 30 % H2O2 and 1 mL of concen-
trated HNO3 to the vial, set it on the hot plate, and heat to
dryness.
10.18 Remove from the hot plate, cool, and add 0.02 mL 0.1
M HNO3.
10.19 Swirl or agitate the vial to dissolve the sample.
10.20 Load 4 µL of the dissolved sample (Step 10.19) on a
filament for analysis in the TIMS.
10.21 Analyze in accordance with the user’s standard oper-
ating procedure for TIMS analysis.
NOTE 4—Follow the requirements for analysis of duplicate samples,
standards, or controls as recommended in the user’s quality control plan.
11. Calculation
11.1 From the certified reference values of the 233U spike
standard (obtained from the certificate of analysis) and any
standardization performed per Step 9.1, calculate the exact
concentration of each isotope (in µg/g) in the spike solution.
µg isotope
g certified solution 5
µmoles U ~total!
g certified solution 3
at fract’n isotope 3 at mass isotope (1)
where the atomic mass for each isotope5 is as follows:
233U 5 233.039627 µg/µmol,
234U 5 234.040945 µg/µmol,
235U 5 235.043922 µg/µmol,
236U 5 236.045561 µg/µmol, and
238U 5 238.050784 µg/µmol.
11.2 Using the weights obtained during standard dilution in
Step 7.8, calculate the exact concentrations of each isotope
present in the working spike solution:
µg isotope
g working solution 5
µg isotope
g certified solution 3
g certified solution ~dispensed!
g working spike solution ~prepared! (2)
11.3 From the sample analysis, obtain the isotopic ratios for
the spiked sample for 233U, 234U, 235U, and 236U to 238U.
11.4 Using the amount of spike added to the sample in Step
10.16 and the concentrations obtained from Step 11.2, calculate
the amounts of spike added for each isotope:
µg isotope added 5 g working spike solution added 3
µg isotope
g working spike solution (3)
11.5 Using the 233U/238U ratio, the 233U added in the spike,
5 CRC Handbook of Chemistry & Physics, 77th Edition (1996–1997), CRC
Press, Inc., Boca Raton, FL, pp. 135–136.
C 1380
2
and the sample mass, calculate the amount of 238U present in
the sample. The value is corrected for any 238U present in the
spiking solution as calculated in Step 11.2:
µg 238U
g sample 5
_R 3 µg 233U added 3 _A 2 µg 238U added
#g sample (4)
where:
R 5 1/R1,
R1 5 233U/238U atomic ratio,
A 5 atomic mass 238U/atomic mass 233U, and
#g sample 5 F1 3 F2 3 W2.
where:
F1 5 weight sample aliquot, g*/total weight, g+,
F2 5 weight used for Dil 1, g**/total weight Dil 1, g ++,
W2 5 weight Dil 1 analyzed, g@,
g* is from Step 10.2;
g** is from Step 10.11;
g+ is weight from Step 10.8—tare of vial and cap Step 10.1;
g++ is from Steps 10.11 and 10.12; and
g@ is from Step 10.15.
11.6 Using the individual ratios from the sample analysis for
234U, 235U, and 236U, calculate the amount of each isotope
present in the sample. The individual values are corrected for
the amount of each isotope present in the spiking solutions as
calculated in Step 11.2:
µg isotope
g sample 5
RX 3 µg 233U added 3 AX 2 µg 23XU added
#g sample (5)
where:
R2 5 23XU/238U atomic ratio,
RX 5 R2/R1 (see Step 11.5), and
AX 5 atomic mass 23XU/atomic mass 233U.
11.7 To calculate the concentration of total uranium, add up
the concentrations calculated for each isotope in Steps 11.5 and
11.6.
12. Precision and Bias
12.1 Aliquots of NBL CRM-129 were prepared and ana-
lyzed over a 12–month period by four analysts. Two hundred
data points were collected. The average for total uranium
content was 0.84788 g U/g oxide with a relative standard
deviation of 0.42 % (the certified value is 0.84773 g U/g
oxide). The average percent 235U content was 0.714 %, with a
relative standard deviation of 0.87 % at the 0.72 % 235U level
(also 200 points collected). The percent 235U value is not yet
certified for NBL CRM-129, but the preliminary value is
0.72 %. The t-test for bias showed no significant bias in this
data at the 95 % confidence level.
13. Keywords
13.1 isotope dilution mass spectrometry (IDMS); uranium
concentration; uranium isotopes
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C 1380
3
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