Design criteria for piping and nozzles program quarterly progress report, April--June 1976. [BWR; PWR]

Technical Report · Thu Jan 27 04:00:00 EST 1977

OSTI ID:7225295

Moore, S E; Bryson, J W

Summaries are given of the reports published by program personnel about stresses to be expected in the bolts, flanges, and hubs of ASME Part B flanged joints and about the appropriate nominal stresses that should be used in conjunction with the ASME Code stress indices for pressure vessel nozzles. Summaries are also given on work currently in progress. This work deals with the structural behavior of reinforced nozzle penetrations in pressure vessels, the fatigue behavior of out-of-round piping elbows, the elastic-response and fatigue failure of piping tees, design analyses for flanged piping joints, and completion and publication of reports on the stress analysis of perforated flat plates, stress indices for socket-welding fittings, and experimental stress analyses of nozzle-to-hemispherical shell models.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 7225295
• Report Number(s): ORNL/NUREG/TM-91
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BWR TYPE REACTORS
CONTAINERS
COOLING SYSTEMS
DESIGN
FAILURES
FATIGUE
FLANGES
JOINTS
MECHANICAL PROPERTIES
NOZZLES
PIPE FITTINGS
PIPE JOINTS
PIPES
PLATES
PRESSURE VESSELS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RESEARCH PROGRAMS
SPECIFICATIONS
STRESS ANALYSIS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS