Standard Practice for Neutron Radiation Damage Simulation by Charged-Particle Irradiation
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Corrosion of metals and alloys — Aqueous corrosion testing of zirconium alloys for use in nuclear power reactors Technical Corrigendum 1
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Standard Practice for Testing Graphite Materials for Gas-Cooled Nuclear Reactor Components
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Standard Practice for Investigating the Effects of Neutron Radiation Damage Using Charged-Particle Irradiation
Corrosion of metals and alloys - Aqueous corrosion testing of zirconium alloys for use in nuclear power reactors (ISO 10270:2022)
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Standard Guide for Use of Protective Coating Standards in Nuclear Power Plants
Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels
Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
Standard Guide for High Temperature Strength Measurements of Graphite Impregnated with Molten Salt