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 E261-16

ASTM E261-16

Superseded Historical

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

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ASTM C852/C852M-16

ASTM C852/C852M-16

Superseded Historical

Standard Guide for Design Criteria for Plutonium Gloveboxes

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ASTM C1553-16

ASTM C1553-16

Superseded Historical

Standard Guide for Drying Behavior of Spent Nuclear Fuel

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ASTM E185-16

ASTM E185-16

Superseded Historical

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

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ASTM D3843-16

ASTM D3843-16

Superseded Historical

Standard Practice for Quality Assurance for Protective Coatings Applied to Nuclear Facilities

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ASTM D5163-16

ASTM D5163-16

Superseded Historical

Standard Guide for Establishing a Program for Condition Assessment of Coating Service Level I Coating Systems in Nuclear Power Plants

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ASTM E523-16

ASTM E523-16

Superseded Historical

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

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ASTM E2215-16

ASTM E2215-16

Superseded Historical

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

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ASTM E944-13e1

ASTM E944-13e1

Superseded Historical

Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance

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ASTM E636-14e1

ASTM E636-14e1

Superseded Historical

Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels

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ASTM E854-14e1

ASTM E854-14e1

Superseded Historical

Standard Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance

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ASTM E1214-11e1

ASTM E1214-11e1

Superseded Historical

Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance

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ASTM E900-15e1

ASTM E900-15e1

Superseded Historical

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

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ASTM C1682-17

ASTM C1682-17

Superseded Historical

Standard Guide for Characterization of Spent Nuclear Fuel in Support of Interim Storage, Transportation and Geologic Repository Disposal

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ASTM C781-19

ASTM C781-19

Superseded Historical

Standard Practice for Testing Graphite Materials for Gas-Cooled Nuclear Reactor Components

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