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ASTM C1476-06

(Test Method)

Standard Test Method for Analysis of Urine for Technetium-99 by Inductively Coupled Plasma-Mass Spectrometry (Withdrawn 2011)

Standard Test Method for Analysis of Urine for Technetium-99 by Inductively Coupled Plasma-Mass Spectrometry (Withdrawn 2011)

SIGNIFICANCE AND USE
Code of Federal Regulations, Title 10, 835.402 states that radiological workers who are likely to receive 100 mrem from intakes are required to be monitored for exposure. For the indirect bioassay for radiological workers exposed to nuclear material containing fission products,  99Tc must be measured in urine samples.
SCOPE
1.1 This test method covers the determination of the concentration of technetium-99 in urine using inductively coupled plasma-mass spectrometry (ICP-MS). This test method can be used to support uranium enrichment and reclamation facility bioassay programs.
1.2 The minimum detectable concentration for this test method, using a quadrupole ICP-MS, is approximately 1.0 ng/L (0.62 Bq/L).
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.
WITHDRAWN RATIONALE
This test method covers the determination of the concentration of technetium-99 in urine using inductively coupled plasma-mass spectrometry (ICP-MS). This test method can be used to support uranium enrichment and reclamation facility bioassay programs.
Formerly under the jurisdiction of Committee C26 on Nuclear Fuel Cycle, this test method was withdrawn in June 2011. This standard is being withdrawn without replacement due to its limited use by industry.

General Information

Status
Withdrawn
Publication Date
31-Dec-2005
Withdrawal Date
31-May-2011
ICS
27.120.30 - Fissile materials and nuclear fuel technology
Technical Committee
C26 - Nuclear Fuel Cycle
Drafting Committee
C26.05 - Methods of Test
Current Stage
Ref Project

Relations

Replaces
ASTM C1476-00 - Standard Test Method for Analysis of Urin for Technetium-99 by Inductively Coupled Plasma-Mass Spectrometry
Effective Date
01-Jan-2006

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ASTM C1476-06 - Standard Test Method for Analysis of Urine for Technetium-99 by Inductively Coupled Plasma-Mass Spectrometry (Withdrawn 2011)ASTM C1476-06 - Standard Test Method for Analysis of Urine for Technetium-99 by Inductively Coupled Plasma-Mass Spectrometry (Withdrawn 2011)
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ASTM C1476-06 - Standard Test Method for Analysis of Urine for Technetium-99 by Inductively Coupled Plasma-Mass Spectrometry (Withdrawn 2011)
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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: C1476 – 06
Standard Test Method for
Analysis of Urine for Technetium-99 by Inductively Coupled
1
Plasma-Mass Spectrometry
This standard is issued under the fixed designation C1476; 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 (´) indicates an editorial change since the last revision or reapproval.
1. Scope D1193 Specification for Reagent Water
2.2 Other Standards:
1.1 This test method covers the determination of the con-
3
ANSI N13.20 Radiological Measurement Quality
centration of technetium-99 in urine using inductively coupled
4
Code of Federal Regulations, Title 10, 835.402
plasma-mass spectrometry (ICP-MS). This test method can be
5
HPS N13.30 Performance Criteria for Radiobioassay
used to support uranium enrichment and reclamation facility
bioassay programs.
3. Terminology
1.2 The minimum detectable concentration for this test
3.1 Definitions:
method, using a quadrupole ICP-MS, is approximately 1.0
3.1.1 instrument check standard, n—standard solutions
ng/L (0.62 Bq/L).
evaluated at given intervals during batch analysis to evaluate
1.3 This standard does not purport to address all of the
instrument stability during analysis.
safety concerns, if any, associated with its use. It is the
3.1.2 internal reference standard, n—standard solutions,
responsibility of the user of this standard to establish appro-
containing an element with similar chemical properties to the
priate safety and health practices and determine the applica-
analyte of interest, added to each calibration standard, check
bility of regulatory limitations prior to use.
standard, and sample for the purpose of monitoring and
2. Referenced Documents correcting for fluctuations in matrix, instrument drift, nebulizer
2
and sample orifice blockages, and aerosol transport effects.
2.1 ASTM Standards:
3.1.3 isobar, n—any nuclide that has the same atomic mass
C1009 Guide for Establishing a QualityAssurance Program
number as another atom, but a different atomic number.
for Analytical Chemistry Laboratories Within the Nuclear
3.2 Acronyms:Acronyms:
Industry
3.2.1 ICP-MS, n—inductively coupled plasma-mass spec-
C1068 GuideforQualificationofMeasurementMethodsby
trometry.
a Laboratory Within the Nuclear Industry
3.2.2 LOD, n—limit of detection.
C1128 Guide for Preparation of Working Reference Mate-
3.2.3 LCS, n—laboratory control standard.
rials for Use in Analysis of Nuclear Fuel Cycle Materials
3.2.4 MDC, n—minimum detectable concentration.
C1156 Guide for Establishing Calibration for a Measure-
3.2.5 %RSD, n—percent relative standard deviation (1 stan-
ment Method Used to Analyze Nuclear Fuel Cycle Mate-
dard deviation/Mean) * 100.
rials
3.2.6 % Bias, n—((mean – true value)/true value) * 100.
C1210 GuideforEstablishingaMeasurementSystemQual-
ity Control Program forAnalytical Chemistry Laboratories
4. Summary of Test Method
Within the Nuclear Industry
4.1 A urine sample is digested in the presence of hydrogen
C1297 Guide for Qualification of Laboratory Analysts for
peroxide to decompose the organic matrix. The pertechnetate
the Analysis of Nuclear Fuel Cycle Materials
ion is selectively separated from ruthenium, actinides, alkali,
and alkaline earth metals in the sample matrix using anion
99
1
This test method is under the jurisdiction ofASTM Committee C26 on Nuclear exchange chromatography.The Tc is eluted with warmed 3.0
Fuel Cycle and is the direct responsibility of Subcommittee C26.05 on Methods of
Test.
3
Current edition approved Jan. 1, 2006. Published January 2006. Originally Available fromAmerican National Standards Institute (ANSI), 25 W. 43rd St.,
approved in 2000. Last previous edition approved in 2000 as C1476 – 00. DOI: 4th Floor, New York, NY 10036, http://www.ansi.org.
4
10.1520/C1476-06. AvailablefromU.S.GovernmentPrintingOfficeSuperintendentofDocuments,
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or 732 N. Capitol St., NW, Mail Stop: SDE, Washington, DC 20401, http://
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM www.access.gpo.gov.
5
Standards volume information, refer to the standard’s Document Summary page on Health Physics Society, “Performance Criteria for Radiobioassay,” HPS
the ASTM website. N13.30, McLean, VA, 1996.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
1

---------------------- Page: 1 ----------------------
C1476 – 06
99
7
M nitric acid. The Tc isotope is analyzed by ICP-MS using a such specifications are available. Other grades may be used,
115 6
suitableinternalstandardsuchas In. Thechemicalrecovery provided it is first ascertained that the re
...

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8.6  
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SCOPE
1.1 This test method covers unirradiated uranium-plutonium mixed oxide having a uranium to plutonium ratio of 2.5 and greater. The presence of larger amounts of plutonium (Pu) that give lower uranium to plutonium ratios may give low analysis results for uranium (U) (1)2, if the amount of plutonium together with the uranium is sufficient to slow the reduction step and prevent complete reduction of the uranium in the allotted time. Use of this test method for lower uranium to plutonium ratios may be possible, especially when 20 mg to 50 mg quantities of uranium are being titrated rather than the 100 mg to 300 mg in the study cited in Ref (1). Confirmation of that information should be obtained before this test method is used for ratios of uranium to plutonium less than 2.5.  
1.2 The amount of uranium determined in the data presented in Section 12 was 20 mg to 50 mg. However, this test method, as stated, contains iron in excess of that needed to reduce the combined quantities of uranium and plutonium in a solution containing 300 mg of uranium with uranium to plutonium ratios greater than or equal to 2.5. Solutions containing up to 300 mg uranium with uranium to plutonium ratios greater than or equal to 2.5 have been analyzed (1) using the reagent volumes and conditions as described in Section 10.  
1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.4 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, health, and environmental practices and determine the applicability of regulatory limitations prior to use. For specific hazard statements, see Section 8.  
1.5 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

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ASTM
ASTM C1703-18(2023)(Practice)
Standard Practice for Sampling of Gaseous Uranium Hexafluoride for Enrichment

SIGNIFICANCE AND USE
5.1 Uranium hexafluoride is normally produced and handled in large (typically 1 to 14-ton) quantities and must, therefore, be characterized by reference to representative samples (see ISO 7195). The samples are used to determine compliance with the applicable commercial specification C787. The quantities involved, physical properties, chemical reactivity, and hazardous nature of UF6 are such that for representative sampling, specially designed equipment must be used and operated in accordance with the most carefully controlled and stringent procedures. This practice can be used by UF6 converters to review the effectiveness of existing procedures or as a guide to the design of equipment and procedures for future use.  
5.2 The intention of this practice is to avoid liquid UF6 sampling once the cylinder has been filled. For safety reasons, manipulation of large quantities of liquid UF6 should be avoided when possible.  
5.3 It is emphasized that this practice is not meant to address conventional or nuclear criticality safety issues.
SCOPE
1.1 This practice covers methods for withdrawing representative sample(s) of uranium hexafluoride (UF6) during a transfer occurring in the gas phase. Such transfer in the gas phase can take place during the filling of a cylinder during a continuous production process, for example the distillation column in a conversion facility. Such sample(s) may be used for determining compliance with the applicable commercial specification, for example Specification C787.  
1.2 Since UF6 sampling is taken during the filling process, this practice does not address any special additional arrangements that may be agreed upon between the buyer and the seller when the sampled bulk material is being added to residues already present in a container (“heels recycle”). Such arrangements will be based on QA procedures such as traceability of cylinder origin (to prevent for example contamination with irradiated material).  
1.3 If the receiving cylinder is purged after filling and sampling, special verifications must be performed by the user to verify the representativity of the sample(s). It is then expected that the results found on volatile impurities with gas phase sampling may be conservative.  
1.4 This practice is only applicable when the transfer occurs in the gas phase. When the transfer is performed in the liquid phase, Practice C1052 should apply. This practice does not apply to gas sampling after the cylinder has been filled since the sample taken will not be representative of the cylinder.  
1.5 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, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.6 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

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