Appropriate nominal stresses for use with ASME Code pressure-loading stress indices for nozzles

Technical Report · Tue Jun 01 04:00:00 EDT 1976

DOI:https://doi.org/10.2172/7247043· OSTI ID:7247043

Rodabaugh, E. C.

This program is part of a cooperative effort with industry to develop and verify analytical methods for assessing the safety of nuclear pressure-vessel and piping-system design. The study of nominal stresses and stress indices described is part of a continuing study of design rules for nozzles in pressure vessels being coordinated by the PVRC Subcommittee on Reinforced Openings and External Loadings. Results from these studies are used by appropriate ASME Code groups in drafting new and improved design rules.

• Research Organization: Battelle Columbus Labs., Ohio (USA)
• OSTI ID: 7247043
• Report Number(s): ORNL/Sub-2913-2
• 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
NOZZLES
PRESSURE VESSELS
PWR TYPE REACTORS
REACTORS
STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS