Influence of crack depth on the fracture toughness of reactor pressure vessel steel
Description
The Heavy Section Steel Technology Program (HSST) at Oak Ridge National Laboratory (ORNL) is investigating the influence of flaw depth on the fracture toughness of reactor pressure vessel (RPV) steel. Recently, it has been shown that, in notched beam testing, shallow cracks tend to exhibit an elevated toughness as a result of a loss of constraint at the crack tip. The loss of constraint takes place when interaction occurs between the elastic-plastic crack-tip stress field and the specimen surface nearest the crack tip. An increased shallow-crack fracture toughness is of interest to the nuclear industry because probabilistic fracture-mechanics evaluations show that shallow flaws play a dominant role in the probability of vessel failure during postulated pressurized-thermal-shock (PTS) events. Tests have been performed on beam specimens loaded in 3-point bending using unirradiated reactor pressure vessel material (A533 B). Testing has been conducted using specimens with a constant beam depth (W = 94 mm) and within the lower transition region of the toughness curve for A533 B. Test results indicate a significantly higher fracture toughness associated with the shallow flaw specimens compared to the fracture toughness determined using deep-crack (a/W = 0.5) specimens. Test data also show little influence of thickness on the fracture toughness for the current test temperature (-60 degree C). 21 refs., 5 figs., 3 tabs
Availability note (English)
MF available from INIS under the Report Number; OSTI as DE91012537; NTIS; INIS; US Govt. Printing Office Dep.Files
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Additional details
Publishing Information
- Imprint Pagination
- 39 p.
- Report number
- CONF-9105188--1
Conference
- Title
- American Society for Testing Materials (ASTM) symposium on constraint effects in fracture.
- Dates
- 8 May 1991.
- Place
- Indianapolis, IN (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22085424
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- CRACK PROPAGATION; CRACKS; DEFECTS; EXPERIMENTAL DATA; FRACTURE MECHANICS; FRACTURE PROPERTIES; NUCLEAR POWER PLANTS; PRESSURE VESSELS; REACTOR MATERIALS; STEEL-MNNIMO
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CONTAINERS; DATA; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; LOW ALLOY STEELS; MANGANESE ALLOYS; MATERIALS; MECHANICAL PROPERTIES; MECHANICS; MOLYBDENUM ADDITIONS; NICKEL ADDITIONS; NUCLEAR FACILITIES; NUMERICAL DATA; POWER PLANTS; STEELS; THERMAL POWER PLANTS
Optional Information
- Contract/Grant/Project number
- Contract AC05-84OR21400
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (USA).