ASTM E636-95

Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E706 (IH)

STANDARD published on 10.10.1995

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The information about the standard:

Designation standards: ASTM E636-95
Note: WITHDRAWN
Publication date standards: 10.10.1995
SKU: NS-47461
The number of pages: 9
Approximate weight : 27 g (0.06 lbs)
Country: American technical standard
Category: Technical standards ASTM

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Additional information

1. Scope

1.1 This guide covers test methods and procedures that can be used in conjunction with, but not as alternatives to, those required by Practice E185 for the surveillance of nuclear reactor vessels. The supplemental test methods 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 also is given for individual test methods. Reference is made to other ASTM test methods for the physical conduct of specimen tests and for raw data acquisition.

2. Referenced Documents

E185-21	Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
E399-23	Standard Test Method for Linear-Elastic Plane-Strain Fracture Toughness of Metallic Materials
E1820-23b	Standard Test Method for Measurement of Fracture Toughness (Includes all amendments and changes 7/14/2023).
E23-23a	Standard Test Methods for Notched Bar Impact Testing of Metallic Materials (Includes all amendments and changes 4/13/2023).
E1921-23b	Standard Test Method for Determination of Reference Temperature, T0, for Ferritic Steels in the Transition Range (Includes all amendments and changes 3/6/2024).
E1253-21	Standard Guide for Reconstitution of Charpy-Sized Specimens
ASME Boiler and Pressure Vessel Code, Section III	Subsection NB (Class 1 Components)
E2298-18	Standard Test Method for Instrumented Impact Testing of Metallic Materials
E2215-19	Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels

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