Coolant mixing and distribution in a transparent reactor model
Description
Following a small break loss-of-coolant accident in a pressurized water reactor, coolant water may be injected at high pressure to help cool the core. This paper reports the results of tests which determined the mixing and distribution of the coolant in a 1/5-scale transparent model of the reactor. The model components included the reactor vessel, cold leg pipe, pump, and loop seal with steam generator and hot leg simulators completing the flow loop. Tests were conducted for a no-refill condition with constant liquid inventory in the facility and zero flow of the primary water. Salt water, dyed red was used for the coolant water to create prototypical density differences in this atmospheric facility. Steady state fluid distribution was determined from flow and density measurements and complete mass balances. Interpretation of the quantitative results was aided by extensive flow visualization studies which include still photographs and motion picture films for all tests. The test parameters included the fluid density ratio, the flow rate of coolant water, and the flow rate of primary water injected in the vessel downcomer to simulate a natural circulation flow through vent valves between the reactor core and the downcomer. Four locations of the small break were tested
Additional details
Publishing Information
- Journal Title
- Am. Soc. Mech. Eng., [Pap.]
- Journal Volume
- 83-WA/HT-38
- Series
- Am. Soc. Mech. Eng., [Pap.].
- Journal Page Range
- 10
- ISSN
- 0402-1215
Conference
- Title
- ASME winter annual meeting.
- Dates
- 13-18 Nov 1983.
- Place
- Boston, MA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16011019
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COOLANTS; CORE FLOODING SYSTEMS; DENSITY; FLOW RATE; HYDRAULICS; HYDRODYNAMICS; LEAKS; LIQUID FLOW; LOSS OF COOLANT; OPACITY; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REACTOR VESSELS; SCALE MODELS; SPECIFICATIONS; TESTING; VALVES
- Descriptors DEC
- ACCIDENTS; CONTAINERS; CONTROL EQUIPMENT; COOLING SYSTEMS; ECCS; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; FLUID FLOW; FLUID MECHANICS; MECHANICS; OPTICAL PROPERTIES; PHYSICAL PROPERTIES; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; STRUCTURAL MODELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-831111--.