Design criteria for piping and nozzles program quarterly progress report for October--December 1976. [PWR; BWR]
Technical Report
·
OSTI ID:7296096
Short summaries are given for studies completed and reports published during the quarter including dimensional controls for piping products, combined loadings on ANSI B16.9 tees, and stresses at reinforced nozzles in spherical shell structures. A summary status report is also given for work currently in progress on the finite element analysis of isolated and closely-spaced nozzles in cylindrical pressure vessels. Finally, a summary report is given on the ASME Code and PVRC committee work including the current status of proposed Code rules revisions that are based, at least in part, on work conducted under the ORNL Design Criteria Program.
- Research Organization:
- Oak Ridge National Lab., Tenn. (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 7296096
- Report Number(s):
- ORNL/NUREG/TM-144
- Country of Publication:
- United States
- Language:
- English
Similar Records
Design criteria for Piping and Nozzles Program. Quarterly progress report, July--September 1976. [BWR; PWR]
Design criteria for piping and nozzles program quarterly progress report, April--June 1976. [BWR; PWR]
Progress report for the design criteria for piping and nozzles program for the two quarterly periods July 1--September 30 and October 1--December 31, 1975
Technical Report
·
Mon Mar 21 23:00:00 EST 1977
·
OSTI ID:7290641
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
Progress report for the design criteria for piping and nozzles program for the two quarterly periods July 1--September 30 and October 1--December 31, 1975
Technical Report
·
Tue Jun 01 00:00:00 EDT 1976
·
OSTI ID:7345906
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
JOINTS
MECHANICAL PROPERTIES
NOZZLES
PIPE FITTINGS
PIPE JOINTS
PIPES
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
JOINTS
MECHANICAL PROPERTIES
NOZZLES
PIPE FITTINGS
PIPE JOINTS
PIPES
PRESSURE VESSELS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RESEARCH PROGRAMS
STRESS ANALYSIS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS