Published April 1992
| Version v1
Report
Pipe fracture behavior under high-rate (seismic) loading - The IPIRG program
- 1. Battelle, Columbus, OH (United States)
Description
Results are summarized from numerous experiments and supporting analyses conducted to investigate the behavior of circumferentially flawed piping and piping systems subjected to high-rate loading typical of seismic events. The investigation included both 'separate effects' experiments on simple pipe specimens with either pure inertial or displacement-controlled loading, and full-scale experiments on a representative piping system with combined loading tested at pressurized water reactor (PWR) conditions
Additional details
Publishing Information
- Imprint Title
- Proceedings of the US Nuclear Regulatory Commission nineteenth water reactor safety information meeting. Volume 1, Plenary session; Pressure vessel and piping integrity; Metallurgy and NDE; Aging and components; Probabilistic risk assessment topics
- Imprint Pagination
- 523 p.
- Journal Page Range
- p. 53-72.
- Report number
- NUREG/CP--0119-Vol.1
Conference
- Title
- 19. Nuclear Regulatory Commission (NRC) water reactor safety information meeting.
- Dates
- 28-30 Oct 1991.
- Place
- Bethesda, MD (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24027093
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; AGING; BEARINGS; BOUNDARY CONDITIONS; BWR TYPE REACTORS; CANADA; CARBON STEELS; COORDINATED RESEARCH PROGRAMS; CRACK PROPAGATION; CRACKS; DAMPING; DEFECTS; DYNAMIC LOADS; ELASTICITY; FINITE ELEMENT METHOD; FRACTURE MECHANICS; FRANCE; ITALY; JAPAN; LEAKS; NONLINEAR PROBLEMS; PIPES; PRESSURIZATION; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; SEISMIC EFFECTS; STAINLESS STEELS; STEEL-CR19NI10; SUPPORTS; SWEDEN; SWITZERLAND; TAIWAN; TEST FACILITIES; TIME DEPENDENCE; UNITED KINGDOM; US NRC; USA; WELDED JOINTS
- Descriptors DEC
- ALLOYS; ASIA; AUSTENITIC STEELS; CALCULATION METHODS; CARBON ADDITIONS; CHINA; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; COOLING SYSTEMS; CORROSION RESISTANT ALLOYS; DEVELOPED COUNTRIES; ENRICHED URANIUM REACTORS; EUROPE; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; JOINTS; MECHANICAL PROPERTIES; MECHANICAL STRUCTURES; MECHANICS; NATIONAL ORGANIZATIONS; NICKEL ALLOYS; NORTH AMERICA; NUMERICAL SOLUTION; POWER REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH PROGRAMS; SAFETY; SCANDINAVIA; STEELS; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-911079--Vol.1.