Simulation of fluid-structure interaction between a drywell penetration and a high energy line break in a BWR
Description
To evaluate the structural integrity of the full pressure steel containment vessel at a piping penetration during a high energy line break (HELB) in a boiling water reactor (BWR) nuclear plant, a computer simulation using RELAP5/FORCE, ADLPIPE and WERCO computer softwares was performed for the fluid-structure interaction considering actual fluid conditions, geometry and system characteristics. The objective of this study is to check the stress field in the drywell penetration assembly to make sure that applicable code requirements are satisfied. The worst condition was found to be the case for the condensate portion of the emergency condensate system (ECS) where mixtures of saturated water and saturated steam discharge at the break location and accelerate inside the penetration assembly. Furthermore, the operating sequence for the system dictates that fluid sources from both ends of the pipe break have to be considered, which consequently increases the blowdown loads. It was ascertained that an effective way to limit the blowdown forces at the penetration is the installation of a flow limiter inside the drywell, specifically, right at the end of the annulus between 10'' process line and 24'' penetration sleeve
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (USA)
- Imprint Title
- Mechanical signature analysis: Machinery vibration, flow-induced vibration, and acoustic noise analysis
- Journal Page Range
- p. 173-180.
Conference
- Title
- 11. biennial conference on mechanical vibration and noise.
- Dates
- 27-30 Sep 1987.
- Place
- Boston, MA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19078501
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- A CODES; BWR TYPE REACTORS; COMPUTERIZED SIMULATION; DYNAMIC LOADS; EVALUATION; F CODES; FLUID-STRUCTURE INTERACTIONS; ON-LINE CONTROL SYSTEMS; PERFORMANCE TESTING; PRESSURE VESSELS; R CODES; REACTOR SAFETY; SPECIFICATIONS; STRESS ANALYSIS; W CODES
- Descriptors DEC
- COMPUTER CODES; CONTAINERS; CONTROL SYSTEMS; ENRICHED URANIUM REACTORS; ON-LINE SYSTEMS; POWER REACTORS; REACTORS; SAFETY; SIMULATION; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS