Effect of cladding on stress intensity factors during normal plant operation
Description
The method for determining the allowable pressure-temperature operating limits is contained in Section XI, Appendix G of the ASME Boiler and Pressure Vessel Code. The Section XI Appendix G approach for calculating these limits uses a fracture mechanics method with conservative assumptions and defined margins to protect the vessel against brittle crack initiation. However, in applying this method, stresses due to the cladding have generally been ignored and are believed to be bounded by the margin on pressure and the assumption of a large quarter-thickness reference flaw. This method is considered to be conservative and adequate for protecting against vessel failure. The Appendix G methodology is currently being reviewed by the Section XI Working Group on Operating Plant Criteria to quantify the safety margins and to improve the overall method. As part of this review, a benchmark problem was recently performed examining the contribution of cladding stresses to the crack tip stress intensity factor for a range of hypothetical reference flaw sizes. This paper describes the insults of this benchmark problem and the effects of cladding on reactor vessel integrity
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-1358-4
- Imprint Title
- Codes and standards for quality engineering. PVP-Volume 285
- Imprint Pagination
- 286 p.
- Journal Page Range
- p. 145-148.
Conference
- Title
- 1994 pressure vessels and piping conference.
- Dates
- 19-23 Jun 1994.
- Place
- Minneapolis, MN (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26021901
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- CLADDING; CRACK PROPAGATION; EXPERIMENTAL DATA; FERRITIC STEELS; LIMITING VALUES; MATHEMATICAL MODELS; PRESSURE VESSELS; PROTECTIVE COATINGS; REACTOR OPERATION; RESIDUAL STRESSES; ROWE YANKEE REACTOR; STAINLESS STEEL-304; STANDARDS; THERMAL STRESSES
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; COATINGS; CONTAINERS; CORROSION RESISTANT ALLOYS; DATA; DEPOSITION; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; NICKEL ALLOYS; NUMERICAL DATA; OPERATION; POWER REACTORS; PWR TYPE REACTORS; REACTORS; STAINLESS STEELS; STEEL-CR19NI10; STEELS; STRESSES; SURFACE COATING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-940613--.