SYMPOSIA PAPER Published: 01 January 1983
STP36798S

J-R Curve Characterization of Irradiated Low-Shelf Nuclear Vessel Steels

Source

The J-R curve behavior of irradiated nuclear pressure vessel steels is characterized in the ductile upper-shelf regime in order to provide a materials basis with which to assess the margin of safety against fracture for water reactor vessels exhibiting a low upper-shelf CV energy. With the single specimen compliance technique, the R-curve is shown to follow a power-law behavior for small crack extension, and this phenomenon has led to a proposed new indexing procedure forJIc. In addition, a specimen size dependence of the R-curve has been suggested by the results of similar compact tension specimens up to 100 mm thick and which have sufficiently deep side grooves to produce a straight crack-front extension.

R-curve data are presented in terms of a J versus T instability diagram which couples material and structural parameters, thereby permitting an analysis to be made of the margin against failure in terms of J. Also, a correlation has been suggested between the R-curve parameters and CV shelf energy; this could enhance the structural significance of CV reactor surveillance data.

Author Information

Loss, FJ
Materials Engineering Associates, Inc., Lanham, Md.
Menke, BH
Materials Engineering Associates, Inc., Lanham, Md.
Hiser, AL
Materials Engineering Associates, Inc., Lanham, Md.
Watson, HE
Naval Research Laboratory, Washington, D.C.
Price: $25.00
Contact Sales
Related
Reprints and Permissions
Reprints and copyright permissions can be requested through the
Copyright Clearance Center
Details
Developed by Committee: E08
Pages: 777–795
DOI: 10.1520/STP36798S
ISBN-EB: 978-0-8031-4870-3
ISBN-13: 978-0-8031-0726-7