Design criteria for Piping and Nozzles Program. Quarterly progress report, July--September 1976. [BWR; PWR]
Technical Report
·
OSTI ID:7290641
Short summaries are given of stress analysis studies of perforated flat plates, a hemispherical shell with a radially attached nozzle, and ANSI Standard B16.5 flanged piping joints. Summary descriptions are also given on work currently in progress, including analyses of isolated and closely-spaced nozzles in cylindrical pressure vessels and the development and validation of computer programs with which to conduct these studies. A summary report is given on ASME and PVRC committee work and the current status of various code rule revisions that are based at least in part on work conducted under the ORNL Design Criteria Program.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 7290641
- Report Number(s):
- ORNL/NUREG/TM-107
- Country of Publication:
- United States
- Language:
- English
Similar Records
Design criteria for piping and nozzles program quarterly progress report for October--December 1976. [PWR; BWR]
Design criteria for piping and nozzles program quarterly progress report, April--June 1976. [BWR; PWR]
Design criteria for the spacing of nozzles and reinforced openings in cylindrical nuclear pressure vessels and pipe. [PWR]
Technical Report
·
Fri Dec 31 23:00:00 EST 1976
·
OSTI ID:7296096
Design criteria for piping and nozzles program quarterly progress report, April--June 1976. [BWR; PWR]
Technical Report
·
Wed Jan 26 23:00:00 EST 1977
·
OSTI ID:7225295
Design criteria for the spacing of nozzles and reinforced openings in cylindrical nuclear pressure vessels and pipe. [PWR]
Technical Report
·
Sun Jan 31 23:00:00 EST 1982
·
OSTI ID:5663204
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
STRESS ANALYSIS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS
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
STRESS ANALYSIS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS