Analytical prediction and experimental verification of reactor safety system injection transient
Conference
·
OSTI ID:10132563
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, Washington, DC (United States)
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 10132563
- 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; Other Information: PBD: [1991]
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
MULTIPHASE FLOW
COMPUTER CODES
REACTOR SHUTDOWN
COMPUTERIZED SIMULATION
SPECIAL PRODUCTION REACTORS
REACTOR SAFETY
HEAT TRANSFER
HYDRAULICS
SAVANNAH RIVER PLANT
FLOW RATE
ENGINEERED SAFETY SYSTEMS
ANALYTICAL SOLUTION
MOCKUP
TESTING
220900
220600
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
MULTIPHASE FLOW
COMPUTER CODES
REACTOR SHUTDOWN
COMPUTERIZED SIMULATION
SPECIAL PRODUCTION REACTORS
REACTOR SAFETY
HEAT TRANSFER
HYDRAULICS
SAVANNAH RIVER PLANT
FLOW RATE
ENGINEERED SAFETY SYSTEMS
ANALYTICAL SOLUTION
MOCKUP
TESTING
220900
220600
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS