A database to evaluate stress intensity factors of elbows with throughwall flaws under combined internal pressure and bending moment
Creators
- 1. Bhabha Atomic Research Centre, Bombay (India). Reactor Design and Development Group
Description
The advent of Leak-Before-Break (LBB) concept has replaced the traditional design basis event of Double Ended Guillotine Break (DEGB) in the design of primary heat transport (PHT) piping. The use of LBB concept requires postulation of largest credible cracks at highly stressed locations and demonstration of its stability under the maximum credible loading conditions. Stress analysis of PHT piping in nuclear power plants shows that the highly stressed piping components are normally elbows and branch tees. This necessitates detailed fracture mechanics evaluation of piping connections by computing Stress Intensity Factor (SIF) and/or J-integral. Simple analytical solutions for evaluation of SIF and J-integral for cracks in straight pipes are readily available in literature. However, the same type of solutions for elbows and tees are limited in open literature. In the present work, a database is generated to evaluate SIF for throughwall circumferential and longitudinal cracks under combined internal pressure and bending moment. Different parameters to characterise a cracked elbow are pipe factor (h), pipe bore radius to thickness ratio (r/t) and crack length. Another parameter (σ) is used to consider the relative magnitude of stresses due to internal pressure and remote bending moment. The database has been used to derive closed form expressions to evaluate SIF for elbow with cracks in terms of the aforementioned parameters. (author). 8 refs., 12 figs., 3 tabs
Availability note (English)
MF available from INIS under the Report Number.Files
25018269.pdf
Files
(459.7 kB)
| Name | Size | Download all |
|---|---|---|
|
md5:9c3b889e5f7853b5f5112a8301dae13c
|
459.7 kB | Preview Download |
Additional details
Publishing Information
- Imprint Pagination
- 24 p.
- Report number
- BARC--1993/E/016
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 25018269
- Subject category
- S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- ANALYTICAL SOLUTION; BENDING; CRACKS; DEFECTS; DYNAMIC LOADS; EVALUATION; F CODES; FINITE ELEMENT METHOD; FRACTURE MECHANICS; FRACTURES; HEAT TRANSFER; LEAKS; NUCLEAR POWER PLANTS; PIPE JOINTS; PIPELINES; PIPES; PRIMARY COOLANT CIRCUITS; REACTORS; RUPTURES; STRESS INTENSITY FACTORS; STRESSES; THEORETICAL DATA
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; COOLING SYSTEMS; DATA; DEFORMATION; ENERGY TRANSFER; FAILURES; INFORMATION; JOINTS; MECHANICS; NUCLEAR FACILITIES; NUMERICAL DATA; NUMERICAL SOLUTION; POWER PLANTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; THERMAL POWER PLANTS