LOCA hydroloads calculations with multidimensional nonlinear fluid/structure interaction. Volume 3. Fluid/structure interaction studies using 3-D STEALTH/WHAMSE. Final report. [PWR]

Technical Report · Mon Nov 01 00:00:00 EST 1982

DOI:https://doi.org/10.2172/6604885· OSTI ID:6604885

Santee, Jr., G. E.; Chang, F. H.; Mortensen, G. A.; Brockett, G. F.; Gross, M. B.; Belytschko, T. B.

This report, the third in a series of reports for RP-1065, describes the final step in the stepwise approach for developing the three-dimensional, nonlinear, fluid-structure interaction methodology to assess the hydroloads on a large PWR during the subcooled portions of a hypothetical LOCA. The final step in the methodology implements enhancements and special modifications to the STEALTH 3D computer program and the WHAMSE 3D computer program. After describing the enhancements, the individual and the coupled computer programs are assessed by comparing calculational results with either analytical solutions or with experimental data. The coupled 3D STEALTH/WHAMSE computer program is then applied to the simulation of HDR Test V31.1 to further assess the program and to investigate the role that fluid-structure interaction plays in the hydrodynamic loading of reactor internals during subcooled blowdown.

• Research Organization: Intermountain Technologies, Inc., Idaho Falls, ID (USA); Science Applications, Inc., San Leandro, CA (USA); Northwestern Univ., Evanston, IL (USA). Technological Inst.
• OSTI ID: 6604885
• Report Number(s): EPRI-NP-1401-Vol.3; ON: DE83900753
• Resource Relation: Other Information: Portions of document are illegible
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LOSS OF COOLANT
HEAT TRANSFER
HYDRAULICS
PWR TYPE REACTORS
COMPUTER CALCULATIONS
HYDRODYNAMICS
PRESSURE GRADIENTS
PRESSURE VESSELS
REACTOR INTERNALS
REACTOR SAFETY
STRESS ANALYSIS
ACCIDENTS
CONTAINERS
ENERGY TRANSFER
FLUID MECHANICS
MECHANICS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled