Marviken full-scale critical-flow tests. Volume 24: results from Test 16

Technical Report · Sat May 01 00:00:00 EDT 1982

OSTI ID:5235911

The sixteenth test in a series of full-scale critical flow tests is described, the test data are presented, and the results are briefly discussed. Test 16 was conducted using a reactor pipe simulator consisting of a rounded entrance followed by a 500 mm, constant diameter test section having a length-to-diameter ratio of 3.6. Test 16 was run with the same initial conditions in the pressure vessel as those specified for Test 11. Compared to Test 11 the test section had been elongated from 1589 mm to 1809 mm. Data were obtained at steam dome pressures which varied from 5.0 to 3.3 MPa and at fluid conditions ranging from 33/sup 0/C subcooled compared to steam dome pressure to saturation with low quality.

• Research Organization: Studsvik Energiteknik AB, Nykoeping (Sweden)
• OSTI ID: 5235911
• Report Number(s): EPRI-NP-2370-Vol.24; ON: DE82904724
• Resource Relation: Other Information: Portions of document are illegible
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
MARVIKEN REACTOR
CRITICAL FLOW
LOSS OF COOLANT
DATA COMPILATION
HYDRAULICS
NOZZLES
PIPES
PRESSURE GRADIENTS
REACTOR SAFETY
TEMPERATURE GRADIENTS
TEST FACILITIES
TWO-PHASE FLOW
ACCIDENTS
BHWR TYPE REACTORS
DATA
ENRICHED URANIUM REACTORS
FLUID FLOW
FLUID MECHANICS
HEAVY WATER COOLED REACTORS
HEAVY WATER MODERATED REACTORS
INFORMATION
MECHANICS
NUMERICAL DATA
POWER REACTORS
REACTOR ACCIDENTS
REACTORS
SAFETY
220900* - Nuclear Reactor Technology- Reactor Safety
210400 - Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated