27.120.30 : Fissile materials and nuclear fuel technology

ASTM C1432-15

ASTM C1432-15

Superseded Historical

Standard Test Method for Determination of Impurities in Plutonium: Acid Dissolution, Ion Exchange Matrix Separation, and Inductively Coupled Plasma-Atomic Emission Spectroscopic (ICP/AES) Analysis

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ASTM C1295-15

ASTM C1295-15

Superseded Historical

Standard Test Method for Gamma Energy Emission from Fission and Decay Products in Uranium Hexafluoride and Uranyl Nitrate Solution

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ASTM C1769-15

ASTM C1769-15

Withdrawn Most Recent

Standard Practice for Analysis of Spent Nuclear Fuel to Determine Selected Isotopes and Estimate Fuel Burnup (Withdrawn 2023)

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ASTM C1233-15

ASTM C1233-15

Superseded Historical

Standard Practice for Determining Equivalent Boron Contents of Nuclear Materials

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ASTM C1187-15

ASTM C1187-15

Superseded Historical

Standard Guide for Establishing Surveillance Test Program for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Fuel Storage Racks In a Pool Environment

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ASTM C1816-15

ASTM C1816-15

Superseded Historical

Standard Practice for The Ion Exchange Separation of Small Volume Samples Containing Uranium, Americium, and Plutonium Prior to Isotopic Abundance and Content Analysis

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ASTM C1817-15

ASTM C1817-15

Superseded Historical

Standard Test Method for The Determination of the Oxygen to Metal (O/M) Ratio in Sintered Mixed Oxide ((U, Pu)O2) Pellets by Gravimetry

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ASTM E481-15

ASTM E481-15

Superseded Historical

Standard Test Method for Measuring Neutron Fluence Rates by Radioactivation of Cobalt and Silver

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ASTM E261-15

ASTM E261-15

Superseded Historical

Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques

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ASTM E265-15

ASTM E265-15

Superseded Historical

Standard Test Method for Measuring Reaction Rates and Fast-Neutron Fluences by Radioactivation of Sulfur-32

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NF ISO 12799, M60-471 (06/2015)

NF ISO 12799, M60-471 (06/2015)

Superseded Historical

Énergie nucléaire - Dosage de la teneur en azote des pastilles frittées d’UO2, (U,Gd)O2 et (U,Pu)O2 - Méthode d'extraction par gaz inerte et méthode de mesurage de la conductivité

€37.33

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NF ISO 15651, M60-472 (04/2015)

NF ISO 15651, M60-472 (04/2015)

Superseded Historical

Énergie nucléaire – Dosage de la teneur totale en hydrogène de poudres de PuO2 et UO2, et de pastilles frittées d’UO2, (U,Gd)O2 et (U,Pu)O2 – Méthode d'extraction par gaz inerte et méthode de mesure de la conductivité

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NF ISO 21483, M60-330 (03/2015)

NF ISO 21483, M60-330 (03/2015)

Superseded Historical

Détermination de la solubilité dans I'acide nitrique du plutonium des pastilles (U, Pu) O2 de combustibles d'oxydes mixtes non irradiés

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NF ISO 15366-1, M60-421-1 (03/2015)

NF ISO 15366-1, M60-421-1 (03/2015)

Superseded Historical

Technologie du combustible nucléaire - Séparation et purification chimiques de l'uranium et du plutonium dans les solutions d'acide nitrique par extraction chromatographique par solvant pour les mesures isotopiques et les analyses par dilution isotopique - Partie 1 : échantillons ayant des teneurs en plutonium de l'ordre du microgramme et en uranium de l'ordre du milligramme

€65.33

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NF ISO 15366-2, M60-421-2 (03/2015)

NF ISO 15366-2, M60-421-2 (03/2015)

Superseded Historical

Technologie du combustible nucléaire - Séparation et purification chimiques de l'uranium et du plutonium dans les solutions d'acide nitrique par extraction chromatographique par solvant pour les mesures isotopiques et les analyses par dilution isotopique - Partie 2 : échantillon ayant des terneurs en plutonium et en uranium de l'ordre du nanogramme et inférieures

€65.33

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