Critical fracture stress and fracture strain models for the prediction of lower and upper shelf toughness in nuclear pressure vessel steels

Journal Article · Mon Oct 01 04:00:00 EDT 1979 · Metall. Trans., A; (United States)

DOI:https://doi.org/10.1007/BF02812022· OSTI ID:5764321

Ritchie, R O; Server, W L; Wullaert, R A

Critical fracture stress and stress modified fracture strain models are utilized to describe the variation of lower and upper shelf fracture toughness with temperature and strain rate for two alloy steels used in the manufacture of nuclear pressure vessels, namely SA533B-1 (HSST Plate 02) and SA302B (Surveillance correlation heat). Both steels have been well characterized with regard to static and dynamic fracture toughness over a wide range of temperatures (-190 to 200/sup 0/C), although valid J/sub Ic/ measurements at upper shelf temperatures are still somewhat scarce. The present work utilizes simple models for the relevant fracture micromechanisms and local failure criteria to predict these variations in toughness from uniaxial tensile properties. Procedures are discussed for modelling the influence of neutron fluence on toughness in irradiated steel, and predictions are derived for the effect of increasing fluence on the variation of lower shelf fracture toughness with temperature in SA533B-1.

• Research Organization: Massachusetts Inst. of Tech., Cambridge
• OSTI ID: 5764321
• Journal Information: Metall. Trans., A; (United States), Journal Name: Metall. Trans., A; (United States) Vol. 10:10; ISSN MTTAB
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360103* -- Metals & Alloys-- Mechanical Properties
ALLOYS
CARBON STEELS
CHARPY TEST
CHEMICAL COMPOSITION
CONTAINERS
CONTROL
COOLING
COOLING SYSTEMS
CRYSTAL STRUCTURE
DUCTILITY
FAILURES
FRACTURE PROPERTIES
FRACTURES
HEATING
IRON ALLOYS
IRON BASE ALLOYS
MECHANICAL PROPERTIES
PRESSURE CONTROL
PRESSURE VESSELS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
STEEL-ASTM-A302
STEEL-ASTM-A533-B
STEELS
STRAINS
TEMPERATURE CONTROL
TENSILE PROPERTIES