Warm prestress effects in fracture-margin assessment of PWR-RPVs

Conference · Tue Jun 01 00:00:00 EDT 1993

OSTI ID:10153667

Shum, D K.M.

This paper examines various issues that would impact the incorporation of warm prestress (WPS) effects in the fracture-margin assessment of reactor pressure vessels (RPVs). By way of an example problem, possible beneficial effects of including type-I WPS in the assessment of an RPV subjected to a small break loss of coolant accident are described. In addition, the need to consider possible loss of constraint effects when interpreting available small specimen WPS-enhanced fracture toughness data is demonstrated through two- and three-dimensional local crack-lip field analyses of a compact tension specimen. Finally, a hybrid correlative-predictive model of WPS base on J-Q theory and the Ritchie-Knott-Rice model is applied to a small scale yielding boundary layer formulation to investigate near crack-tip fields under varying degrees of loading and unloading.

• Research Organization: Oak Ridge National Lab., TN (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 10153667
• Report Number(s): CONF-930803-10; ON: DE93013511
• Resource Relation: Conference: 12. biennial conference for the International Association for Structural Mechanics in Reactor Technology (SMIRT 12),Stuttgart (Germany),16-26 Aug 1993; Other Information: PBD: [1993]
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
PWR TYPE REACTORS
PRESSURE VESSELS
FRACTURE PROPERTIES
STAINLESS STEELS
STEEL-ASTM-A533-B
LOSS OF COOLANT
REACTOR SAFETY
CRACKS
CRACK PROPAGATION
STRESSES
220900
210200
360103
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
MECHANICAL PROPERTIES