Fluid-structure interaction during LOCA blowdown
- 1. Electric Power Research Institute, Palo Alto, CA 94303
Description
A methodology for realistically analyzing three-dimensional fluid-structure interaction effects and the resulting hydrodynamic loads during the subcooled portion of a hypothetical loss-of-coolant accident in a pressurized water reactor is discussed. The methodology uses a hydrodynamic computer program, STEALTH 3D coupled with a structural response program, WHAMSE 3D, to calculate the dynamic interaction of fluid and structure during a reactor vessel blowdown. This coupled program is user oriented and highly versatile in modeling the various components in complex reactor systems. Assessment of the methodology is provided by STEALTH/WHAMSE 3D calculations of blowdown tests in the German Battelle-Frankfurt RS-16B facility (Test DWR5) and the HDR facility (Tests V31.1 and V32). The calculations are described and the results compared with experimental data. Agreement between the calculational results and experimental data is good
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- LaGrange Park, IL (USA)
- ISBN
- 0-89448-110-X
- Imprint Title
- Thermal hydraulics of nuclear reactors
- Journal Page Range
- p. 778-791.
Conference
- Title
- 2. international topical meeting on nuclear reactor thermal hydraulics (ANS).
- Dates
- 11-13 Jan 1983.
- Place
- Santa Barbara, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17089445
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BLOWDOWN; COMPUTER CALCULATIONS; COMPUTERIZED SIMULATION; DATA PROCESSING; FLUID-STRUCTURE INTERACTIONS; HDR REACTOR; HYDRODYNAMICS; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR VESSELS; S CODES; SUBCOOLING; W CODES
- Descriptors DEC
- ACCIDENTS; BWR TYPE REACTORS; COMPUTER CODES; CONTAINERS; COOLING; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FLUID MECHANICS; MECHANICS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS