ASTM E636-02
Historical Standard: ASTM E636-02 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E 706 (IH)
SUPERSEDED (see Active link, below)
ASTM E636
1. Scope
1.1 This guide discusses test procedures that can be used in conjunction with, but not as alternatives to, those required by Practice E 185 for the surveillance of nuclear reactor vessels. The supplemental mechanical property tests outlined permit the acquisition of additional information on radiation-induced changes in fracture toughness, notch ductility, and tensile strength properties of the reactor vessel steels.
1.2 This guide provides recommendations for the preparation of test specimens for irradiation, and identifies special precautions and requirements for reactor surveillance operations and postirradiation test planning. Guidance on data reduction and computational procedures is also given. Reference is made to other ASTM test methods for the physical conduct of specimen tests and for raw data acquisition.
2. Referenced Documents (purchase separately) The documents listed below are referenced within the subject standard but are not provided as part of the standard.
ASTM Standards
E23 Test Methods for Notched Bar Impact Testing of Metallic Materials
E185 Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
E399 Test Method for Linear-Elastic Plane-Strain Fracture Toughness K Ic of Metallic Materials
E1253 Guide for Reconstitution of Irradiated Charpy-Sized Specimens
E1820 Test Method for Measurement of Fracture Toughness
E1921 Test Method for Determination of Reference Temperature, To, for Ferritic Steels in the Transition Range
E2215 Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
E2298 Test Method for Instrumented Impact Testing of Metallic Materials
ASME Standards
ASMEBoilerandPressur Subsection NB (Class 1 Components)Keywords
fracture toughness; irradiation; notch ductility; nuclear reactor vessels; surveillance (of nuclear reactor vessels)
; Irradiance/irradiation; Neutron flux/fluence; Nuclear reactor vessels--surveillance; Radiation exposure--nuclear materials/applications ;
ICS Code
ICS Number Code 27.120.10 (Reactor engineering)
DOI: 10.1520/E0636-02
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