Published June 1980
| Version v1
Report
Marviken Critical Flow Test Program
Description
A multinational project, the Marviken Full Scale Critical Flow Tests conducted twenty-seven tests to obtain critical mass flow data for short nozzle geometries (200 to 509 mm diameters with length to diameter ratios from 0.3 to 3.7) comparable to pipe sizes present in world nuclear reactor stations. Typical data are presented and discussed. The nozzle inlet pressures ranged from 5.2 to 2.6 MPa with the fluid subcooled as much as 500C to low quality saturation. A maximum nozzle mass flow rate of 14 Mg/s was measured. The data provide an important link between the previously available small scale critical mass flow rate data and existing operational hardware
Additional details
Publishing Information
- Imprint Title
- Thermal Reactor Safety
- Journal Page Range
- p. 119-126.
- Report number
- CONF-800403--(Vol.1)
Conference
- Title
- ANS thermal reactor safety meeting.
- Dates
- 8 - 11 Apr 1980.
- Place
- Knoxville, TN, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11570334
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CRITICAL FLOW; HYDRAULICS; LIQUID FLOW; NOZZLES; PRESSURE GRADIENTS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR SAFETY; SPATIAL DISTRIBUTION
- Descriptors DEC
- COOLING SYSTEMS; DISTRIBUTION; FLUID FLOW; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS