Analytical prediction and experimental verification of reactor safety system injection transient

Conference · Tue Jan 01 00:00:00 EST 1991

OSTI ID:5758739

Roy, B N; Nomm, E

This paper describes the computer code that was developed for thermal hydraulic transient analysis of mixed phase fluid system and the flow tests that were carried out to validate the Code. A full scale test facility was designed to duplicate the Supplementary Shutdown System (SSS) of Savannah River Production Reactors. Several steady state and dynamic flow tests were conducted simulating the actual reactor injection transients. A dynamic multiphase fluid flow code was developed and validated with experimental results and utilized for system performance predictions and development of technical specifications for reactors. 3 refs.

• Research Organization: Westinghouse Savannah River Co., Aiken, SC (United States)
• Sponsoring Organization: USDOE; USDOE, Washington, DC (United States)
• DOE Contract Number: AC09-89SR18035
• OSTI ID: 5758739
• Report Number(s): WSRC-MS-91-161; CONF-9111194-1; ON: DE92009822
• Resource Relation: Conference: American Society of Mechanical Engineers (ASME) winter meeting, Atlanta, GA (United States), 15 Nov 1991
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
MULTIPHASE FLOW
COMPUTER CODES
REACTOR SHUTDOWN
COMPUTERIZED SIMULATION
SPECIAL PRODUCTION REACTORS
ANALYTICAL SOLUTION
ENGINEERED SAFETY SYSTEMS
FLOW RATE
HEAT TRANSFER
HYDRAULICS
MOCKUP
REACTOR SAFETY
SAVANNAH RIVER PLANT
TESTING
ENERGY TRANSFER
FLUID FLOW
FLUID MECHANICS
MECHANICS
NATIONAL ORGANIZATIONS
PRODUCTION REACTORS
REACTORS
SAFETY
SHUTDOWN
SIMULATION
STRUCTURAL MODELS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
220900* - Nuclear Reactor Technology- Reactor Safety
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors