First spinning cylinder test analysis by using local approach to fracture
Creators
- 1. Service Reacteurs Nucleaires et Echangeurs, Electricite de France, Moret s/Loing (France)
Description
In recent years, several experimental programs on large scale specimens were organized to evaluate capabilities of the fracture mechanics concepts employed structural integrity assessment of PWR pressure vessels. One test of these programs, the first spinning cylinder test, performed by Northern Research Laboratories, involved the rotation of a 200 mm thick cylinder containing a full length axial flaw to an angular speed to 2600 rpm at the temperature of 290 degrees C. A J-R curve was derived from experimental results and proved considerably larger J-values than the curve corresponding to small scale compact tension specimens tests. A geometry effect (scale, load, or size effect), was experimentally pointed out and exhibited the problem of transferability of toughness data from small scale to large scale specimens. An original analysis of this test, by means of local approach to fracture, is presented in this paper. Both compact tension specimen and spinning cylinder fracture behavior were computed by using a continuum damage mechanics model developed at EDF. Damage evolution in the structure related to cavities nucleation and growth, is directly calculated from stress and strain fields in the vicinity of the crack tip. This model enables crack initiation prediction, and also crack growth simulation. Then, combining numerical results and J-contour integral calculation provides a numerical J-R curve characteristic of the structure behavior regarding to ductile tearing
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-0816-5
- Imprint Title
- Service experience in operating plants 1991
- Imprint Pagination
- 126 p.
- Journal Page Range
- p. 17-22.
Conference
- Title
- 1991 American Society of Mechanical Engineers (ASME) pressure vessels and piping conference.
- Dates
- 23-27 Jun 1991.
- Place
- San Diego, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23071392
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DESIGN; DYNAMIC LOADS; FINITE ELEMENT METHOD; FRACTURE MECHANICS; GEOMETRY; MATERIALS TESTING; PERFORMANCE TESTING; PWR TYPE REACTORS; REACTOR VESSELS; RESEARCH PROGRAMS; STRESS ANALYSIS; TWO-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- CALCULATION METHODS; CONTAINERS; ENRICHED URANIUM REACTORS; MATHEMATICS; MECHANICS; NUMERICAL SOLUTION; POWER REACTORS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-910602--.