Actions for Emergency cooling simulation tests on an electrically heated channel typical of SRP (Savannah River Laboratory) reactor fuel channels - RIG B [electronic resource].
Emergency cooling simulation tests on an electrically heated channel typical of SRP (Savannah River Laboratory) reactor fuel channels - RIG B [electronic resource].
- Published
- Washington, D.C : United States. Dept. of Energy. Office of the Assistant Secretary for Defense Programs, 1990.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description
- Pages: (8 pages) : digital, PDF file
- Additional Creators
- Westinghouse Savannah River Company, United States. Department of Energy. Office of the Assistant Secretary for Defense Programs, and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- Emergency cooling simulation tests were conducted on a single electrically heated test channel representative of Savannah River Plant fuel assembly flow channels. The primary objective was to investigate downflow, air-water hydraulic flow conditions that lead to the onset of a runaway thermal excursion in the range of superficial liquid and gas velocities, 1.4 m/sec and 1 m/sec, respectively. The thermal excursion power normalized by the power to reach fluid outlet saturation conditions, or R-factor, was found to decrease from values close to 2, at annular flow conditions to approximately 0.8 at low to zero void fractions. 3 refs., 9 figs.
- Report Numbers
- E 1.99:wsrc-ms-90-42
E 1.99: conf-900917--30
conf-900917--30
wsrc-ms-90-42 - Subject(s)
- Other Subject(s)
- Fuel Channels
- Heat Transfer
- Hydraulics
- Loss Of Coolant
- Reactor Safety Experiments
- Special Production Reactors
- Eccs
- Air
- Alloy Nuclear Fuels
- Annular Fuel Elements
- Boundary Conditions
- Chernobylsk-4 Reactor
- Design
- Excursions
- Fuel Assemblies
- Pipes
- Reactor Accidents
- Reactor Cores
- Reactor Safety
- Risk Assessment
- Ruptures
- Savannah River Plant
- Simulation
- Usa
- Void Fraction
- Water
- Accidents
- Energy Sources
- Energy Transfer
- Engineered Safety Systems
- Enriched Uranium Reactors
- Failures
- Fluid Mechanics
- Fluids
- Fuel Elements
- Fuels
- Gases
- Graphite Moderated Reactors
- Hydrogen Compounds
- Lwgr Type Reactors
- Materials
- Mechanics
- National Organizations
- North America
- Nuclear Fuels
- Oxygen Compounds
- Power Reactors
- Production Reactors
- Reactor Channels
- Reactor Components
- Reactor Materials
- Reactor Protection Systems
- Reactors
- Safety
- Solid Fuels
- Thermal Reactors
- Us Aec
- Us Doe
- Us Erda
- Us Organizations
- Water Cooled Reactors
- Note
- Published through SciTech Connect.
01/01/1990.
"wsrc-ms-90-42"
" conf-900917--30"
"DE91005132"
American Nuclear Society topical meeting on safety of non-commercial nuclear reactor research and irradiation facilities, Boise, ID (USA), 30 Sep - 3 Oct 1990.
Guerrero, H.N. - Funding Information
- AC09-89SR18035
View MARC record | catkey: 14371481