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ASTM C1221-10

(Test Method)

Standard Test Method for Nondestructive Analysis of Special Nuclear Materials in Homogeneous Solutions by Gamma-Ray Spectrometry

Standard Test Method for Nondestructive Analysis of Special Nuclear Materials in Homogeneous Solutions by Gamma-Ray Spectrometry

SIGNIFICANCE AND USE
This test method is a nondestructive means of determining the nuclide concentration of a solution for special nuclear material accountancy, nuclear safety, and process control.
It is assumed that the nuclide to be analyzed is in a homogeneous solution (Practice C1168).
The transmission correction makes the test method independent of matrix (solution elemental composition and density) and useful over several orders of magnitude of nuclide concentrations. However, a typical configuration will normally span only two to three orders of magnitude because of detector dynamic range.
The test method assumes that the solution-detector geometry is the same for all measured items. This can be accomplished by requiring that the liquid height in the sidelooking geometry exceeds the detector field of view defined by the collimator. For the upward-looking geometry, a fixed solution fill height must be maintained and vials of identical radii must be used unless the vial radius exceeds the field of view defined by the collimator.
Since gamma-ray systems can be automated, the test method can be rapid, reliable, and not labor intensive.
This test method may be applicable to in-line or off-line situations.
SCOPE
1.1 This test method covers the determination of the concentration of gamma-ray emitting special nuclear materials dissolved in homogeneous solutions. The test method corrects for gamma-ray attenuation by the solution and its container by measurement of the transmission of a beam of gamma rays from an external source (Refs. (1), (2), and (3)).  
1.2 Two solution geometries, slab and cylinder, are considered. The solution container that determines the geometry may be either a removable or a fixed geometry container. This test method is limited to solution containers having walls or a top and bottom of equal transmission through which the gamma rays from the external transmission correction source must pass.
1.3 This test method is typically applied to radionuclide concentrations ranging from a few milligrams per litre to several hundred grams per litre. The assay range will be a function of the specific activity of the nuclide of interest, the physical characteristics of the solution container, counting equipment considerations, assay gamma-ray energies, solution matrix, gamma-ray branching ratios, and interferences.
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 and health practices and determine the applicability of regulatory limitations prior to use. For specific hazards, see Section 9.

General Information

Status
Historical
Publication Date
28-Feb-2010
ICS
27.120.30 - Fissile materials and nuclear fuel technology
Technical Committee
C26 - Nuclear Fuel Cycle
Drafting Committee
C26.10 - Non Destructive Assay
Current Stage
Ref Project

Relations

Replaces
ASTM C1221-92(2004) - Standard Test Method for Nondestructive Analysis of Special Nuclear Materials in Homogeneous Solutions by Gamma-Ray Spectrometry
Effective Date
01-Mar-2010
Replaced By
ASTM C1221-10(2018) - Standard Test Method for Nondestructive Analysis of Special Nuclear Materials in Homogeneous Solutions by Gamma-Ray Spectrometry
Effective Date
01-Apr-2018
Referred By
ASTM C1592/C1592M-21 - Standard Guide for Making Quality Nondestructive Assay Measurements
Effective Date
01-Mar-2010
Referred By
ASTM C1490-14(2023) - Standard Guide for the Selection, Training and Qualification of Nondestructive Assay (NDA) Personnel
Effective Date
01-Mar-2010

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ASTM C1221-10 - Standard Test Method for Nondestructive Analysis of Special Nuclear Materials in Homogeneous Solutions by Gamma-Ray SpectrometryASTM C1221-10 - Standard Test Method for Nondestructive Analysis of Special Nuclear Materials in Homogeneous Solutions by Gamma-Ray Spectrometry
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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:C1221 −10
Standard Test Method for
Nondestructive Analysis of Special Nuclear Materials in
1
Homogeneous Solutions by Gamma-Ray Spectrometry
This standard is issued under the fixed designation C1221; 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 C1133Test Method for Nondestructive Assay of Special
Nuclear Material in Low-Density Scrap and Waste by
1.1 This test method covers the determination of the con-
Segmented Passive Gamma-Ray Scanning
centration of gamma-ray emitting special nuclear materials
C1490GuidefortheSelection,TrainingandQualificationof
dissolved in homogeneous solutions. The test method corrects
Nondestructive Assay (NDA) Personnel
for gamma-ray attenuation by the solution and its container by
C1592Guide for Nondestructive Assay Measurements
measurement of the transmission of a beam of gamma rays
2 C1673Terminology of C26.10 NondestructiveAssay Meth-
from an external source (Refs. (1), (2), and (3)).
ods
1.2 Two solution geometries, slab and cylinder, are consid-
C1168PracticeforPreparationandDissolutionofPlutonium
ered.The solution container that determines the geometry may
Materials for Analysis
be either a removable or a fixed geometry container. This test
E181Test Methods for Detector Calibration andAnalysis of
method is limited to solution containers having walls or a top
Radionuclides
and bottom of equal transmission through which the gamma
4
2.2 ANSI Standards:
rays from the external transmission correction source must
ANSI N15.20Guide to Calibrating Nondestructive Assay
pass.
Systems
1.3 This test method is typically applied to radionuclide ANSI N15.35Guide to Preparing Calibration Material for
concentrations ranging from a few milligrams per litre to
NondestructiveAssaySystemsthatCountPassiveGamma
several hundred grams per litre. The assay range will be a Rays
function of the specific activity of the nuclide of interest, the
ANSI N15.37Guide to the Automation of Nondestructive
physical characteristics of the solution container, counting Assay Systems for Nuclear Material Control
equipment considerations, assay gamma-ray energies, solution
ANSI N42.14American National Standard for Calibration
matrix, gamma-ray branching ratios, and interferences.
and Use of Germanium Spectrometers for the Measure-
ment of Gamma-Ray Emission Rates of Radionuclides
1.4 This standard does not purport to address all of the
ANSI/IEEE 645Test Procedures for High-Purity Germa-
safety concerns, if any, associated with its use. It is the
nium Detectors for Ionizing Radiation
responsibility of the user of this standard to establish appro-
priate safety and health practices and determine the applica-
3. Terminology
bility of regulatory limitations prior to use. For specific
hazards, see Section 9. 3.1 Fordefinitionsoftermsusedinthistestmethod,referto
Committee C26.10’s Terminology standard, C1673.
2. Referenced Documents
4. Summary of Test Method
3
2.1 ASTM Standards:
4.1 Manynuclearmaterialsspontaneouslyemitgammarays
with energies and intensities characteristic of the decaying
1
ThistestmethodisunderthejurisdictionofASTMCommitteeC26onNuclear
nuclide. The analysis for these nuclear materials is accom-
Fuel Cycle and is the direct responsibility of Subcommittee C26.10 on Non
plished by selecting appropriate gamma rays and measuring
Destructive Assay.
their intensity to identify and quantify the nuclide.
Current edition approved March 1, 2010. Published April 2010. Originally
approved in 1992. Last previous edition approved in 2004 as C1221–92(2004). 4.1.1 The gamma-ray spectrum of a portion of solution is
DOI: 10.1520/C1221-10.
obtained with a collimated, high resolution gamma-ray detec-
2
Theboldfacenumbersinparenthesesrefertothelistofreferencesattheendof
tor.
this test method.
3
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
4
Standards volume information, refer to the standard’s Document Summary page on Available fromAmerican National Standards Institute (ANSI), 25 W. 43rd St.,
the ASTM website. 4th Floor, New York, NY 10036, http://www.ansi.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
C1221−10
4.1.2 Count-rate-dependent losses are determined and cor-
rections are made for these losses.
4.1.3 A correction factor for gamma-ray attenuation in the
solution and its container is determined from the measurement
of the transmitted intensity of an external gamma-
...

This document is not anASTM standard and is intended only to provide the user of anASTM standard an indication of what changes have been made to the previous version. Because
it may not be technically possible to adequately depict all changes accurately,ASTM recommends that users consult prior editions as appropriate. In all cases only the current version
of the standard as published by ASTM is to be considered the official document.
Designation:C1221–92 (Reapproved 2004) Designation: C1221 – 10
Standard Test Method for
Nondestructive Analysis of Special Nuclear Materials in
1
Homogeneous Solutions by Gamma-Ray Spectrometry
This standard is issued under the fixed designation C1221; 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
1.1 This test method covers the determination of the concentration of gamma-ray emitting special nuclear materials dissolved
in homogeneous solutions. The test method corrects for gamma-ray attenuation by the samplesolution and its container by
2
measurement of the transmission of a beam of gamma rays from an external source (Refs. (1), (2), and (3)).
1.2 Two samplesolution geometries, slab and cylinder, are considered. The samplesolution container that determines the
geometrymaybeeitheraremovableorafixedgeometrycontainer.Thistestmethodislimitedtosamplesolutioncontainershaving
walls or a top and bottom of equal transmission through which the gamma rays from the external transmission correction source
must pass.
1.3 This test method is typically applied to radionuclide concentrations ranging from a few milligrams per litre to several
hundred grams per litre. The assay range will be a function of the specific activity of the nuclide of interest, the physical
characteristics of the samplesolution container, counting equipment considerations, assay gamma-ray energies, samplesolution
matrix, gamma-ray branching ratios, and interferences.
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 and health practices and determine the applicability of regulatory
limitations prior to use. For specific hazards, see Section 9.
2. Referenced Documents
2.1 ASTM Standards:
C859Terminology Relating to Nuclear Materials
3
C982Guide for Selecting Components for Energy-Dispersive X-Ray Fluorescence (XRF) Systems ASTM Standards:
C1133 Test Method for Nondestructive Assay of Special Nuclear Material in Low-Density Scrap and Waste by Segmented
Passive Gamma-Ray Scanning
C1490 Guide for the Selection, Training and Qualification of Nondestructive Assay (NDA) Personnel
C1592 Guide for Nondestructive Assay Measurements
C1673 Terminology of C26.10 Nondestructive Assay Methods
C1168 Practice for Preparation and Dissolution of Plutonium Materials for Analysis
E181 Test Methods for Detector Calibration and Analysis of Radionuclides
4
2.2 ANSI Standards:
ANSI N15.20 Guide to Calibrating Nondestructive Assay Systems
ANSI N15.35 Guide to Preparing Calibration Material for Nondestructive Assay Systems that Count Passive Gamma Rays
ANSI N15.37 Guide to the Automation of Nondestructive Assay Systems for Nuclear Material Control
ANSI N42.14 American National Standard for Calibration and Use of Germanium Spectrometers for the Measurement of
Gamma-Ray Emission Rates of Radionuclides
ANSI/IEEE 645 Test Procedures for High-Purity Germanium Detectors for Ionizing Radiation
2.3 U.S. Nuclear Regulatory Commission Regulatory Guides:
1
This test method is under the jurisdiction ofASTM Committee C26 on Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.10 on Non-Destructive
Assay.
Current edition approved June 1, 2004. Published July 2004. Originally approved in 1992. Last previous edition approved in 1998 as C1221-92 (1998). DOI:
10.1520/C1221-92R04.on Non Destructive Assay.
Current edition approved March 1, 2010. Published April 2010. Originally approved in 1992. Last previous edition approved in 2004 as C1221–92 (2004). DOI:
10.1520/C1221-92R10.
2
The boldface numbers in parentheses refer to the list of references at the end of this test method.
3
ForreferencedASTMstandards,visittheASTMwebsite,www.astm.org,orcontactASTMCustomerServiceatservice@astm.org.For Annual Book of ASTM Standards
volume information, refer to the standard’s Document Summary page on the ASTM website.
4
Available from American National Standards Institute (ANSI), 25 W. 43rd St., 4th Floor, New York, NY 10036, http://www.ansi.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
1

---------------------- Page: 1 ----------------------
C1221 – 10
Regulatory Guide 5.9,Rev. 2, Guidel
...

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ASTM C1268-23(Test Method)
Standard Test Method for Quantitative Determination of 241Am in Plutonium by Gamma-Ray Spectrometry

SIGNIFICANCE AND USE
5.1 This test method allows the determination of 241Am in a plutonium solution without separation of the americium from the plutonium. It is generally applicable to any solution containing 241Am.  
5.2 The 241Am in solid plutonium materials may be determined when these materials are dissolved (see Practice C1168).  
5.3 When the plutonium solution contains unacceptable levels of fission products or other materials, this method may be used following a tri-n-octylphosphine oxide (TOPO) extraction, ion exchange or other similar separation techniques (see Test Methods C758 and C759).  
5.4 This test method is less subject to interferences from plutonium than alpha counting since the energy of the gamma ray used for the analysis is better resolved from other gamma rays than the alpha particle energies used for alpha counting.  
5.5 The minimal sample preparation reduces the amount of sample handling and exposure to the analyst.  
5.6 This test method is applicable only to homogeneous solutions. This test method is not suitable for solutions containing solids.  
5.7 Solutions containing 241Am at concentrations as little as 1 × 10−5 g/L may be analyzed using this method. The lower limit depends on the detector used and the counting geometry. Solutions containing high concentrations may be analyzed following an appropriate dilution.
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1.1 This test method covers the quantitative determination of 241Am by gamma-ray spectrometry in plutonium nitrate solution samples that do not contain significant amounts of radioactive fission products or other high specific activity gamma-ray emitters.  
1.2 This test method can be used to determine the 241Am in samples of plutonium metal, oxide and other solid forms, when the solid is appropriately sampled and dissolved.  
1.3 The values stated in SI units are to be regarded as standard. Additionally, the non-SI units of electron volts, kiloelectron volts, and liters 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.  
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ASTM C1168-23(Practice)
Standard Practice for Preparation and Dissolution of Plutonium Materials for Analysis

SIGNIFICANCE AND USE
5.1 Plutonium and uranium mixtures are used as nuclear reactor fuels. For use as a nuclear reactor fuel, the material must meet certain criteria for combined uranium and plutonium content, effective fissile content, and impurity content as described in Specifications C757 and C833. After dissolution using one of the procedures described in this practice, the material is assayed for plutonium and uranium to determine if the content is correct as specified by the purchaser.  
5.2 Unique plutonium materials, such as alloys, compounds, and scrap metals, are typically dissolved with various acid mixtures or by fusion with various fluxes. Many plutonium salts are soluble in hydrochloric acid. One or more of the procedures included in this practice may be effective for some of these materials; however their applicability to a particular plutonium material shall be verified by the user.
SCOPE
1.1 This practice is a compilation of dissolution techniques for plutonium materials that are applicable to the test methods used for characterizing these materials. Dissolution treatments for the major plutonium materials assayed for plutonium or analyzed for other components are listed. Aliquots of the dissolved materials are dispensed on a mass basis when one of the analyses must be of high precision, such as plutonium assay; otherwise they are dispensed on a volume basis.  
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1.3 One or more of the procedures in this practice may be applicable to unique plutonium materials, such as alloys, compounds, and scrap materials. The user must determine the applicability of this practice to such materials.  
1.4 The treatments, in order of presentation, are as follows:    
Procedure Number  
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Section  
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Dissolution of Plutonium Metal with Hydrochloric Acid at Room Temperature  
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2  
Dissolution of Plutonium Metal with Hydrochloric Acid and Heating  
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10  
Open-Vessel (with Reflux Condenser) Dissolution of Mixed Oxide Pellets  
18  
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1.1 This specification covers finished sintered and ground (U, Pu)O2 pellets for use in light water reactors. It applies to (U, Pu)O2 pellets containing a plutonium mass fraction up to 15 % (that is, mass of Pu divided by the sum of masses U, Pu, and Am yielding 0.15 or less).  
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1.1 This terminology standard contains terms, definitions, descriptions of terms, nomenclature, and explanations of acronyms and symbols specifically associated with standards under the jurisdiction of Committee C26 on Nuclear Fuel Cycle. The content of this terminology standard may also be applicable to documents not under the jurisdiction of Committee C26, in which case this terminology standard may be referenced in those documents.  
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SIGNIFICANCE AND USE
4.1 Materials handling equipment operability and long-term integrity are concerns that originate during the design and fabrication sequences. Such concerns are most efficiently addressed during one or the other of these stages. Equipment operability and integrity can be compromised during handling and installation sequences. For this reason, the subject equipment should be handled and installed under closely controlled and supervised conditions.  
4.2 This guide is intended as a supplement to other standards (Section 2, Referenced Documents), and to federal and state regulations, codes, and criteria applicable to the design of equipment intended for this use.  
4.3 This guide is intended to be generic and to apply to a wide range of types and configurations of materials handling equipment.  
4.4 The term materials handling equipment is used herein in a generic sense. It includes manipulators, cranes, carts or bogies, and special equipment for handling tools and material in hot cells.  
4.5 This service imposes stringent requirements on the quality and the integrity of the equipment, as follows:  
4.5.1 Boots and similar protective covers should not restrict movement of the equipment, should be properly sealed to the equipment and should withstand the radiation, cell atmosphere, dust, cell temperatures, chemical exposures, and cleaning and decontamination reagents, and also resist snags and tearing.  
4.5.2 Materials handling equipment should be capable of withstanding rigorous chemical cleaning and decontamination procedures.  
4.5.3 Materials handling equipment should be designed and fabricated to remain dimensionally stable throughout its life cycle.  
4.5.4 Attention to fabrication tolerances is necessary to allow the proper fit-up between components for the proper installation and mounting of materials handling equipment in hot cells, for example, when parts or components are being replaced. Fabrication tolerances should be controlled to provide sufficie...
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1.1 Intent:  
1.1.1 This guide covers materials handling equipment used in hot cells (shielded cells) for the processing and handling of nuclear and radioactive materials. The intent of this guide is to aid in the selection and design of materials handling equipment for hot cells in order to minimize equipment failures and maximize the equipment utility.  
1.1.2 It is intended that this guide record the principles and caveats that experience has shown to be essential to the design, fabrication, installation, maintenance, repair, replacement, and decontamination and decommissioning of materials handling equipment capable of meeting the stringent demands of operating, dependably and safely, in a hot cell environment where operator visibility is limited due to the radiation exposure hazards.  
1.1.3 This guide may apply to materials handling equipment in other radioactive remotely operated facilities such as suited entry repair areas and canyons, but does not apply to materials handling equipment used in commercial power reactors.  
1.1.4 This guide covers mechanical master-slave manipulators and electro-mechanical manipulators, but does not cover electro-hydraulic manipulators.  
1.2 Applicability:  
1.2.1 This guide is intended to be applicable to equipment used under one or more of the following conditions:
1.2.1.1 The materials handled or processed constitute a significant radiation hazard to man or to the environment.
1.2.1.2 The equipment will generally be used over a long-term life cycle (for example, in excess of two years), but equipment intended for use over a shorter life cycle is not excluded.
1.2.1.3 The equipment can neither be accessed directly for purposes of operation or maintenance, nor can the equipment be viewed directly, for example, without shielded viewing windows, periscopes, or a video monitoring system.  
1.3 User Caveats:  
1.3.1 This standard is not a substitute for applied engin...

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ASTM
ASTM C1108-23(Test Method)
Standard Test Method for Plutonium by Controlled-Potential Coulometry

SIGNIFICANCE AND USE
5.1 Factors governing selection of a method for the determination of plutonium include available quantity of sample, sample purity, desired level of reliability, and equipment.  
5.1.1 This test method determines 5 mg to 20 mg of plutonium with prior dissolution using Practice C1168.  
5.1.2 This test method calculates plutonium mass fraction in solutions and solids using an electrical calibration based upon Ohm’s Law and the Faraday Constant.  
5.1.3 Chemical standards are used for quality control. When prior chemical separation of plutonium is necessary to remove interferences, the quality control standards should be included with each chemical separation batch (9).  
5.2 Fitness for Purpose of Safeguards and Nuclear Safety Application—Methods intended for use in safeguards and nuclear safety applications shall meet the requirements specified by Guide C1068 for use in such applications.
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1.1 This test method describes the determination of dissolved plutonium from unirradiated nuclear-grade (that is, high-purity) materials by controlled-potential coulometry. Controlled-potential coulometry may be performed in a choice of supporting electrolytes, such as 0.9 mol/L (0.9 M) HNO3, 1 mol/L (1 M) HClO4, 1 mol/L (1 M) HCl, 5 mol/L (5 M) HCl, and 0.5 mol/L (0.5 M) H2SO4. Limitations on the use of selected supporting electrolytes are discussed in Section 6. Optimum quantities of plutonium for this procedure are 5 mg to 20 mg.  
1.2 Plutonium-bearing materials are radioactive and toxic. Adequate laboratory facilities, such as gloved boxes, fume hoods, controlled ventilation, etc., along with safe techniques must be used in handling specimens containing these materials.  
1.3 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.  
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.  
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 C1204-14(2023)(Test Method)
Standard Test Method for Uranium in Presence of Plutonium by Iron(II) Reduction in Phosphoric Acid Followed by Chromium(VI) Titration

SIGNIFICANCE AND USE
4.1 Factors governing selection of a method for the determination of uranium include available quantity of sample, sample purity, desired level of reliability, and equipment availability.  
4.2 This test method is suitable for samples between 20 mg to 300 mg of uranium, is applicable to fast breeder reactor (FBR)-mixed oxides having a uranium to plutonium ratio of 2.5 and greater, is tolerant towards most metallic impurity elements usually specified for FBR-mixed oxide fuel, and uses no special equipment.  
4.3 The ruggedness of the titration method has been studied for both the volumetric (6) and the weight (7) titration of uranium with dichromate.
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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 C1347-08(2023)(Practice)
Standard Practice for Preparation and Dissolution of Uranium Materials for Analysis

SIGNIFICANCE AND USE
4.1 The materials covered that must meet ASTM specifications are uranium metal and uranium oxide.  
4.2 Uranium materials are used as nuclear reactor fuel. For this use, these materials must meet certain criteria for uranium content, uranium-235 enrichment, and impurity content, as described in Specifications C753 and C776. The material is assayed for uranium to determine whether the content is as specified.  
4.3 Uranium alloys, refractory uranium materials, and uranium containing scrap and ash are unique uranium materials for which the user must determine the applicability of this practice. In general, these unique uranium materials are dissolved with various acid mixtures or by fusion with various fluxes.
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1.1 This practice covers dissolution treatments for uranium materials that are applicable to the test methods used for characterizing these materials for uranium elemental, isotopic, and impurities determinations. Dissolution treatments for the major uranium materials assayed for uranium or analyzed for other components are listed.  
1.2 The treatments, in order of presentation, are as follows:    
Procedure Title  
Section  
Dissolution of Uranium Metal and Oxide with Nitric Acid  
8.1  
Dissolution of Uranium Oxides with Nitric Acid and Residue
Treatment  
8.2  
Dissolution of Uranium-Aluminum Alloys in Hydrochloric Acid
with Residue Treatment  
8.3  
Dissolution of Uranium Scrap and Ash by Leaching with Nitric
Acid and Treatment of Residue by Carbonate Fusion  
8.4  
Dissolution of Refractory Uranium-Containing Material by
Carbonate Fusion  
8.5  
Dissolution of Uranium—Aluminum Alloys
Uranium Scrap and Ash, and Refractory
Uranium-Containing Materials by
Microwave Treatment  
8.6  
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. Specific hazards statements are given in Section 7.  
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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