Analytical prediction and experimental verification of reactor safety system injection transient
Abstract
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.
- Authors:
- Publication Date:
- Research Org.:
- Westinghouse Savannah River Co., Aiken, SC (United States)
- Sponsoring Org.:
- USDOE, Washington, DC (United States)
- OSTI Identifier:
- 10132563
- Report Number(s):
- WSRC-MS-91-161; CONF-9111194-1
ON: DE92009822
- DOE Contract Number:
- AC09-89SR18035
- Resource Type:
- Conference
- 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
- Subject:
- 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
Citation Formats
Roy, B N, and Nomm, E. Analytical prediction and experimental verification of reactor safety system injection transient. United States: N. p., 1991.
Web.
Roy, B N, & Nomm, E. Analytical prediction and experimental verification of reactor safety system injection transient. United States.
Roy, B N, and Nomm, E. 1991.
"Analytical prediction and experimental verification of reactor safety system injection transient". United States. https://www.osti.gov/servlets/purl/10132563.
@article{osti_10132563,
title = {Analytical prediction and experimental verification of reactor safety system injection transient},
author = {Roy, B N and Nomm, E},
abstractNote = {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.},
doi = {},
url = {https://www.osti.gov/biblio/10132563},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Dec 31 00:00:00 EST 1991},
month = {Tue Dec 31 00:00:00 EST 1991}
}
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