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ASTM C696-19

Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide Powders and Pellets

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NORMA vydána dne 1.11.2019

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Informace o normě:

Označení normy: ASTM C696-19
Datum vydání normy: 1.11.2019
Kód zboží: NS-976690
Počet stran: 8
Přibližná hmotnost: 24 g (0.05 liber)
Země: Americká technická norma
Kategorie: Technické normy ASTM

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Anotace textu normy ASTM C696-19 :

Keywords:

impurity content, isotopic composition, stoichiometry, uranium content, uranium dioxide,, ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)

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Significance and Use

4.1 Uranium dioxide is used as a nuclear-reactor fuel. In order to be suitable for this purpose, the material must meet certain criteria for uranium content, stoichiometry, isotopic composition, and impurity content. These test methods are designed to show whether or not a given material meets the specifications for these items as described in Specifications C753 and C776.

4.1.1 An assay is performed to determine whether the material has the minimum uranium content specified on a dry weight basis.

4.1.2 The stoichiometry of the oxide powder is useful for predicting its sintering behavior in the pellet production process.

4.1.3 Determination of the isotopic content of the uranium in the uranium dioxide powder is made to establish whether the effective fissile content is in compliance with the purchaser's specifications.

4.1.4 Impurity content is determined to ensure that the maximum concentration limit of certain impurity elements is not exceeded. Determination of impurities is also required for calculation of the equivalent boron content (EBC).

4.1.5 Determination of the oxygen-to-uranium ratio is performed on the completed pellets to determine whether they have the appropriate stoichiometry for optimal performance during irradiation.

1. Scope

1.1 These test methods cover procedures for the chemical, mass spectrometric, and spectrochemical analysis of nuclear-grade uranium dioxide powders and pellets to determine compliance with specifications.

1.2 Units—The values stated in SI units are to be regarded as standard. The values given in parentheses are for information only.

1.3 The analytical procedures appear in the following order:

Sections

Uranium by Ferrous Sulfate Reduction in Phosphoric Acid and Dichromate Titration Method

Uranium and Oxygen Uranium Atomic Ratio by the Ignition (Gravimetric) Impurity Correction Method

Carbon (Total) by Direct Combustion-Thermal Conductivity Method

Total Chlorine and Fluorine by Pyrohydrolysis Ion-Selective Electrode Method

Moisture by the Coulometric, Electrolytic Moisture Analyzer Method

8 – 15

Nitrogen by the Kjeldahl Method

16 – 23

Isotopic Uranium Composition by Multiple-Filament Surface Ionization Mass Spectrometric Method

Spectrochemical Determination of Trace Elements in High-Purity Uranium Dioxide

Silver, Spectrochemical Determination of, by Gallium Oxide Carrier D-C Arc Technique

Rare Earths by Copper Spark-Spectrochemical Method

Impurity Elements by a Spark-Source Mass Spectrographic Method

Surface Area by Nitrogen Absorption Method

24 – 30

Total Gas in Reactor-Grade Uranium Dioxide Pellets

Thorium and Rare Earth Elements by Spectroscopy

Hydrogen by Inert Gas Fusion

Uranium Isotopic Analysis by Mass Spectrometry

1.4 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.

2. Referenced Documents

C1408-16	Standard Test Method for Carbon (Total) in Uranium Oxide Powders and Pellets By Direct Combustion-Infrared Detection Method
C1413-18	Standard Test Method for Isotopic Analysis of Hydrolyzed Uranium Hexafluoride and Uranyl Nitrate Solutions by Thermal Ionization Mass Spectrometry
E402-02	Standard Test Method for Spectrographic Analysis of Uranium Oxide (U₃O₈)by Gallium Oxide-Carrier Technique (Withdrawn 2007)
E130-08	Standard Practice for Designation of Shapes and Sizes of Graphite Electrodes (Withdrawn 2013)
E115-97	Standard Practice for Photographic Processing in Optical Emission Spectrographic Analysis (Withdrawn 2002)
D1193-06(2018)	Standard Specification for Reagent Water
C1287-18	Standard Test Method for Determination of Impurities in Nuclear Grade Uranium Compounds by Inductively Coupled Plasma Mass Spectrometry
C753-16a(2021)	Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder (Includes all amendments and changes 10/22/2021).
C1457-18	Standard Test Method for Determination of Total Hydrogen Content of Uranium Oxide Powders and Pellets by Carrier Gas Extraction
C1502-16	Standard Test Method for Determination of Total Chlorine and Fluorine in Uranium Dioxide and Gadolinium Oxide
C1347-08(2023)	Standard Practice for Preparation and Dissolution of Uranium Materials for Analysis
C776-17(2022)	Standard Specification for Sintered Uranium Dioxide Pellets for Light Water Reactors
C1453-19	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
C1267-17(2022)	Standard Test Method for Uranium by Iron (II) Reduction in Phosphoric Acid Followed by Chromium (VI) Titration in the Presence of Vanadium
C761-18	Standard Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Uranium Hexafluoride

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