27.120.10 : Reactor engineering

ASTM E521-96(2009)e1

ASTM E521-96(2009)e1

Superseded Historical

Standard Practice for Neutron Radiation Damage Simulation by Charged-Particle Irradiation

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ISO 10270:1995/Cor 1:1997

ISO 10270:1995/Cor 1:1997

Superseded Historical

Corrosion of metals and alloys — Aqueous corrosion testing of zirconium alloys for use in nuclear power reactors Technical Corrigendum 1

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ASTM C781-20

ASTM C781-20

Active Most Recent

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

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ASTM E521-25

ASTM E521-25

Superseded Historical

Standard Practice for Investigating the Effects of Neutron Radiation Damage Using Charged-Particle Irradiation

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UNE-EN ISO 10270:2022

UNE-EN ISO 10270:2022

Active Most Recent

Corrosion of metals and alloys - Aqueous corrosion testing of zirconium alloys for use in nuclear power reactors (ISO 10270:2022)

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ASTM D5144-08(2016)

ASTM D5144-08(2016)

Superseded Historical

Standard Guide for Use of Protective Coating Standards in Nuclear Power Plants

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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Superseded Historical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 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Superseded Historical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 E636-14e1

ASTM E636-14e1

Superseded Historical

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

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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Superseded Historical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 C781-19

ASTM C781-19

Superseded Historical

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

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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Superseded Historical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 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 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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