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

Conference · Fri Jan 01 00:00:00 EST 1993

OSTI ID:6593375

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: USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6593375
• Report Number(s): CONF-930803-10; ON: DE93013511
• Resource Relation: Conference: 12. biennial conference for the International Association for Structural Mechanics in Reactor Technology, Stuttgart (Germany), 16-20 Aug 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
PRESSURE VESSELS
FRACTURE PROPERTIES
PWR TYPE REACTORS
STAINLESS STEELS
STEEL-ASTM-A533-B
CRACK PROPAGATION
CRACKS
LOSS OF COOLANT
REACTOR SAFETY
STRESSES
ACCIDENTS
ALLOYS
CARBON STEELS
CONTAINERS
ENRICHED URANIUM REACTORS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
MECHANICAL PROPERTIES
POWER REACTORS
REACTOR ACCIDENTS
REACTORS
SAFETY
STEELS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
360103 - Metals & Alloys- Mechanical Properties