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ASTM C1022-93

(Test Method)

Standard Test Methods for Chemical and Atomic Absorption Analysis of Uranium-Ore Concentrate

Standard Test Methods for Chemical and Atomic Absorption Analysis of Uranium-Ore Concentrate

SCOPE
1.1 These test methods cover procedures for the chemical and atomic absorption analysis of uranium-ore concentrates to determine compliance with the requirements prescribed in Specification C 967.
1.2 The analytical procedures appear in the following order:SectionsUranium by Ferrous Sulfate Reduction-Potassium Dichromate Titrimetry9Nitric Acid-Insoluble Uranium10 to 18Extractable Organic Material19 to 26Arsenic by Diethyldithiocarbamate (Photometric Method)27 to 36Carbonate by CO2 Gravimetry37 to 43Fluoride by Ion-Selective Electrode44 to 51Halides by Volhard Titration52 to 59Moisture by Loss of Weight at 110°C60 to 66Phosphorus by Spectrophotometry67 to 75Silicon by Gravimetry76 to 82Thorium by the Thorin (Photometric) Method83 to 91Calcium, Iron, Magnesium, Molybdenum, Titanium, and Vana-dium by Atomic Absorption Spectrophotometry92 to 101Potassium and Sodium by Atomic Absorption Spectrophotometry102 to 111Boron by Spectrophotometry112 to 121
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. Specific precautionary statements are given in Sections 7, 32, and Note 14.

General Information

Status
Historical
Publication Date
09-Jan-2002
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

Replaced By
ASTM C1022-02 - Standard Test Methods for Chemical and Atomic Absorption Analysis of Uranium-Ore Concentrate
Effective Date
10-Jan-2002

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ASTM C1022-93 - Standard Test Methods for Chemical and Atomic Absorption Analysis of Uranium-Ore ConcentrateASTM C1022-93 - Standard Test Methods for Chemical and Atomic Absorption Analysis of Uranium-Ore Concentrate
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ASTM C1022-93 - Standard Test Methods for Chemical and Atomic Absorption Analysis of Uranium-Ore Concentrate
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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: C 1022 – 93
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 Test Methods for
Chemical and Atomic Absorption Analysis of Uranium-Ore
1
Concentrate
This standard is issued under the fixed designation C 1022; 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.
4
1. Scope Methods for Chemical Analysis of Metals
1.1 These test methods cover procedures for the chemical
3. Terminology
and atomic absorption analysis of uranium-ore concentrates to
3.1 Definitions—For definitions of terms used in these test
determine compliance with the requirements prescribed in
methods, refer to Terminology C 859.
Specification C 967.
1.2 The analytical procedures appear in the following order:
4. Significance and Use
Sections
4.1 The test methods in this standard are designed to show
Uranium by Ferrous Sulfate Reduction—Potassium Dichromate
whether a given material meets the specifications prescribed in
Titrimetry 9 to 16
Nitric Acid-Insoluble Uranium 17 to 25
Specification C 967.
Extractable Organic Material 26 to 33
4.2 Because of the variability of matrices of uranium-ore
Arsenic by Diethyldithiocarbamate (Photometric Method) 34 to 43
concentrate and the lack of suitable reference or calibration
Carbonate by CO Gravimetry 44 to 50
2
Fluoride by Ion-Selective Electrode 51 to 58
materials, the precision and bias of these test methods should
Halides by Volhard Titration 59 to 66
be established by each individual laboratory that will use them.
Moisture by Loss of Weight at 110°C 67 to 73
The precision and bias statements given for each test method
Phosphorus by Spectrophotometry 74 to 82
Silicon by Gravimetry 83 to 89
are those reported by various laboratories and can be used as a
Thorium by the Thorin (Photometric) Method 90 to 98
guideline.
Calcium, Iron, Magnesium, Molybdenum, Titanium, and Vana-
dium by Atomic Absorption Spectrophotometry 99 to 108 4.3 Instrumental test methods such as X-ray fluorescence
Potassium and Sodium by Atomic Absorption
and emission spectroscopy can be used for the determination of
Spectrophotometry 109 to 118
some impurities where such equipment is available.
Boron by Spectrophotometry 119 to 128
1.3 This standard does not purport to address all of the 5. Interferences
safety concerns, if any, associated with its use. It is the
5.1 Interferences are identified in the individual test meth-
responsibility of the user of this standard to establish appro-
ods.
priate safety and health practices and determine the applica-
5.2 Ore concentrates are of a very variable nature; therefore,
bility of regulatory limitations prior to use. Specific precau-
all interferences are very difficult to predict. The individual
tionary statements are given in Sections 7, 39, and Note 16.
user should verify the applicability of each procedure for
specific ore concentrates.
2. Referenced Documents
2.1 ASTM Standards:
6. Reagents
C 761 Test Methods for Chemical, Mass Spectrometric,
6.1 Purity of Reagents—Reagent grade chemicals shall be
Spectrochemical, Nuclear, and Radiochemical Analysis of
used in all tests. Unless otherwise indicated, it is intended that
2
Uranium Hexafluoride
all reagents shall conform to the specifications of the Commit-
2
C 859 Terminology Relating to Nuclear Materials
tee on Analytical Reagents of the American Chemical Society,
2
C 967 Specification for Uranium Ore Concentrate
5
where such specifications are available. Other grades may be
3
D 1193 Specification for Reagent Water
used, provided it is first ascertained that the reagent is of
E 60 Practice for Photometric and Spectrophotometric
1 4
These test methods are under the jurisdiction of ASTM Committee C-26 on Annual Book of ASTM Standards, Vol 03.05.
5
Nuclear Fuel Cycle and are the direct responsibility of Subcommittee C26.05 on Reagent Chemicals, American Chemical Society Specifications, American
Methods of Test. Chemical Society, Washington, DC. For suggestions on the testing of reagents not
Current edition approved Nov. 15, 1993. Published February 1994. Originally listed by the American Chemical Society, see Analar Standards for Laboratory
published as C 1022 – 84. Last previous edition C 1022 – 84 (1990). Chemicals, BDH Ltd., Poole, Dorset, U.K., and the United States Pharmacopeia
2
Annual Book of ASTM Standards, Vol 12.01. and National Formulary, U.S. Pharmaceutical Convention, Inc. (USPC), Rockville,
3
Annual Book of ASTM Standards, Vol 11.01. MD.
1

---------------------- Page: 1 ----------------------
C 1022
suffici
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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.  
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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.  
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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.  
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Procedure Number  
Procedure Title  
Section  
1  
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2  
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5  
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8  
Open-Vessel (with Reflux Condenser) Dissolution of Mixed Oxide Powder  
16  
9  
Closed-Vessel Hot Block Dissolution of Plutonium Oxide Powder  
17  
10  
Open-Vessel (with Reflux Condenser) Dissolution of Mixed Oxide Pellets  
18  
1.5 The values stated in SI units are to be regarded as standard. The non-SI unit of molarity (M) is also to be regarded as standard. Values in parentheses (non-SI units), where provided, are for information only and are not considered standard.  
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Standard Test Method for Isotopic Analysis of Uranium Hexafluoride by Single–Standard Gas Source Multiple Collector Mass Spectrometer Method

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5.1 Uranium hexafluoride is a basic material used to produce nuclear reactor fuel. To be suitable for this purpose, the material must meet criteria for isotopic composition. This test method is designed to determine whether the material meets the requirements described in Specifications C787 and C996.
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ASTM C833-23(Specification)
Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pellets for Light Water Reactors

ABSTRACT
This specification covers finished sintered and ground (uranium-plutonium) dioxide pellets for use in thermal reactors. It applies to uranium-plutonium dioxide pellets containing plutonium additions up to 15 % weight. The diversity of manufacturing methods shall be recognized by which uranium-plutonium dioxide pellets are produced and the many special requirements for chemical and physical characterization that may be imposed by the operating conditions to which the pellets will be subjected in specific reactor systems. The following are different chemical requirements that shall be determined: uranium content, plutonium content, impurity content, stoichiometry, moisture content, gas content, and americium-241 content. Nuclear requirements such as isotopic content, plutonium equivalent at a given date, equivalent boron content, and reactivity shall also be determined. Physical properties of the pellets like dimensions, density, grain size, pore morphology, plutonium-oxide homogeneity, plutonium-oxide particle size, plutonium-oxide particle distribution, integrity, and surface cracks shall be determined as well. The surfaces of finished pellets shall be visually free of loose chips, oil, macroscopic inclusions, and foreign materials. An estimate of the fuel pellet irradiation stability shall be obtained unless adequate allowance for such effects are factored into the fuel rod design. The estimate of the stability shall consist of either conformance to the thermal stability test as specified in the or by adequate correlation of manufacturing process or microstructure to in-reactor behavior, or both.
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Standard Guide for Design, Fabrication, and Installation of Nuclear Fuel Dissolution Facilities

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1.2 Applicability and Exclusions:  
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1.2.1.1 Dissolution Procedures—Fuel compositions, fuel element geometry, and fuel manufacturing methods are subject to continuous change in response to the demands of new reactor designs and requirements. These changes preclude the inclusion of design considerations for dissolvers suitable for the processing of all possible fuel types. This guide will only address equipment associated with dissolution cycles for those fuels that have been used most extensively in reactors as of the time of issue (or revision) of this guide. (See Appendix X1.)  
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ASTM C859-23(Terminology)
Standard Terminology Relating to Nuclear Materials

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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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ASTM C1554-18(2023)(Guide)
Standard Guide for Materials Handling Equipment for Hot Cells

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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.  
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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...
SCOPE
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.  
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Standard Practice for Sampling of Gaseous Uranium Hexafluoride for Enrichment

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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.  
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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.  
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Standard Practice for Preparation and Dissolution of Uranium Materials for Analysis

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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.  
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SCOPE
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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ASTM
ASTM C1165-23(Test Method)
Standard Test Method for Determining Plutonium by Controlled-Potential Coulometry in H2SO4 at a Platinum Working Electrode

SIGNIFICANCE AND USE
5.1 This test method is used to ascertain whether or not materials meet specifications for plutonium concentration or plutonium mass fraction.  
5.1.1 The materials (nuclear grade plutonium nitrate solutions, plutonium metal, plutonium oxide powder, and mixed oxide and carbide powders and pellets) to which this test method applies are subject to nuclear safeguards regulations governing their possession and use. However, adherence to this test method does not automatically guarantee regulatory acceptance of the resulting safeguards measurements. It remains the sole responsibility of the user of this test method to ensure that its application to safeguards has the approval of the proper regulatory authorities.  
5.1.2 When used in conjunction with appropriate certified reference materials (CRMs), this test method can demonstrate traceability to the international measurements system (SI).  
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.  
5.3 A chemical calibration of the coulometer is necessary for accurate results.
FIG. 1 Example of a Cell Design Used at Los Alamos National Laboratory (LANL)
SCOPE
1.1 This test method covers the determination of milligram quantities of plutonium in unirradiated uranium-plutonium mixed oxide having a U/Pu ratio range of 0.1 to 10. This test method is also applicable to plutonium metal, plutonium oxide, uranium-plutonium mixed carbide, various plutonium compounds including fluoride and chloride salts, and plutonium solutions.  
1.2 The recommended amount of plutonium for each aliquant in the coulometric analysis is 5 mg to 10 mg. Precision worsens for lower amounts of plutonium, and elapsed time of electrolysis becomes impractical for higher amounts of plutonium.  
1.3 The quantity values stated in SI units are to be regarded as standard. The quantity values with non-SI units are given in parentheses 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. Specific precautionary statements are given in Section 9.  
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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  • Standard
    6 pages
    English language
    sale 15% off