27.120 : Nuclear energy engineering

27.120.01

Nuclear energy in general

27.120.10

Reactor engineering

27.120.20

Nuclear power plants. Safety

27.120.30

Fissile materials and nuclear fuel technology

27.120.99

Other standards related to nuclear energy
ASTM C1187-20

ASTM C1187-20

Superseded Historical

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

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ASTM C992-20

ASTM C992-20

Superseded Historical

Standard Specification for Boron-based Neutron Absorbing Material Systems for Use in Nuclear Fuel Storage Racks in Pool Environment

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ASTM E900-15e2

ASTM E900-15e2

Superseded Historical

Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials

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ASTM D8377-21

ASTM D8377-21

Superseded Historical

Standard Guide for High Temperature Strength Measurements of Graphite Impregnated with Molten Salt

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ASTM E523-21

ASTM E523-21

Superseded Historical

Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Copper

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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Superseded Historical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 E185-15

ASTM E185-15

Superseded Historical

Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels

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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Superseded Historical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Superseded Historical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Superseded Historical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 C787-15

ASTM C787-15

Superseded Historical

Standard Specification for Uranium Hexafluoride for Enrichment

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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 C996-15

ASTM C996-15

Superseded Historical

Standard Specification for Uranium Hexafluoride Enriched to Less Than 5 % 235U

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ASTM E2215-15

ASTM E2215-15

Superseded Historical

Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels

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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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