ASTM-E636 2009
$40.63
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 |
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 |
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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 |