ASTM-E636 2002

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E636-02 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E 706 (IH)

Published By	Publication Date	Number of Pages
ASTM	2002	9

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Categories: 27.120.10 - Reactor engineering, ASTM

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Description

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.

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PDF Pages	PDF Title
1	Scope Referenced Documents Significance and Use Supplemental Mechanical Property Test
2	General Test Requirements FIG. 1
3	Fracture Toughness Test FIG. 2
5	Precracked Charpy Impact Test Instrumented Charpy V-Notch Impact Test
6	FIG. 3 FIG. 4 FIG. 5
7	Keywords X1. METHOD FOR APPROXIMATING DYNAMIC TOUGHNESS FROM PRECRACKED CHARPY IMPACT SPECIMENS FOR ELASTIC-PLASTIC FRACTURE MODE X1.1 Scope X1.2 Determination of Critical Forces and Energies X1.3 Calculation of Wm, Corrected Crack Initiation Energy X1.4 Calculations of JPCI, the J Integral Value at Maximum Force from Precracked Charpy X1.5 Calculation of Approximate Dynamic Toughness
8	REFERENCES TABLE X1.1

Additional information

Standard Title	E636-02 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E 706 (IH)
Published Code	ASTM
Publication Date	2002
Pages Count	9
ICS Codes	27.120.10 - Reactor engineering

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ASTM-E636 2002

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