Implicit safety margins in the ASME code acceptance criteria for flaws in austenitic piping
Description
The Main Committee of the ASME Code recently approved evaluation procedures and acceptance criteria for flaws in austenitic piping. These revisions will appear in the Winter 1983 Addenda to Section XI of the ASME Code. The allowable flaw sizes were specified in IWB-364-1 as a function of applied stress and loading category (e.g., normal and upset, emergency and faulted conditions). The allowable flaw sizes were intended to provide a minimum safety margin of 2.77 for normal and upset conditions and 1.39 for emergency and faulted conditions. Recently, concerns have been expressed on whether the Code allowable flaw sizes do indeed provide the intended safety margins. The purpose of this is to demonstrate the technical basis for the acceptance criteria and confirm the Code margins by considering selected examples
Files
Additional details
Publishing Information
- Imprint Title
- CSNI specialist meeting on leak-before-break in nuclear reactor piping: proceedings
- Journal Page Range
- p. 264-271.
- Report number
- NUREG/CP--0051
Conference
- Title
- CSNI leak-before-break conference.
- Dates
- 1-2 Sep 1983.
- Place
- Monterey, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16068263
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AUSTENITIC STEELS; BENDING; DEFECTS; FLOW STRESS; FRACTURE PROPERTIES; FRACTURES; INSPECTION; LOSS OF COOLANT; NUCLEAR POWER PLANTS; PIPES; REACTOR COOLING SYSTEMS; REACTOR SAFETY; SAFETY ENGINEERING; SIZE; STRESSES
- Descriptors DEC
- ACCIDENTS; ALLOYS; CARBON ADDITIONS; COOLING SYSTEMS; DEFORMATION; FAILURES; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; NUCLEAR FACILITIES; POWER PLANTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; SAFETY; STEELS; THERMAL POWER PLANTS