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ASTM-E636 2009

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E636-09 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E 706 (IH)

Published By Publication Date Number of Pages
ASTM 2009 8
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1.1 This guide discusses test procedures that can be used in conjunction with, but not as alternatives to, those required by Practices E 185 and E 2215 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 yield 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 and ISO test methods for the physical conduct of specimen tests and for raw data acquisition.

PDF Catalog

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 Fracture Toughness Test at Impact Loading Rates
6 Instrumented Charpy V-Notch Impact Test
FIG. 3
FIG. 4
FIG. 5
7 Keywords
X1. METHOD FOR CALCULATING DYNAMIC REFERENCE TEMPERATURE FROM PRECRACKED CHARPY IMPACT SPECIMENS TESTED AT IMPACT LOADING RATES IN THE DUCTILE TO BRITTLE TRANSITION REGION
X1.1 Scope
X1.2 Determination of Critical Values at Specimen Fracture
X1.3 Calculation of Jcd, (Dynamic J-Integral at Specimen Fracture)
8 X1.4 Calculation of Estimated KJc,d(Dynamic Stress Intensity factor at Specimen Fracture)
REFERENCES
ASTM-E636 2009
$40.63