Primary system pressure (max):2.2 MPa
Volumetric scale:1/1
Height scale:1
Number of loops:4
HL inner diam.:748.48 mm
CL inner diam.:748.48 mm
Notes:
UPTF was used for tests on mixing of flows of water flows with different boron concentrations in the cold legs, and the RPV downcomer annulus
Number:4
Number of sim. fuel Rods:49408
Diameter:10.7 mm
Pitch:14.3 mm
Number:4
Emmerling R. et al., 1988, 2D/3-D Program Upper Plenum Test Facility, UPTF: Program and System Description, Siemens/KWU, U9 414/88/023, Erlangen (G)
Glaeser H., 1989, Analysis of downcomer and tie plate countercurrent flow in the Upper Plenum Test Facility (UPTF), NURETH-4 Conf., Karlsruhe (G)
Glaeser H., Karwat H., 1993, The contribution of UPTF experiments to resolve some scale-up uncertainties in countercurrent two phase flow, J. Nuclear Engineering and Design, 145
Liebert J., Emmerling R., 1998, UPTF experiment Flow phenomena during full-scale loop seal clearing of a PWR, J. Nuclear Engineering and Design, 179
Umminger K., Liebert J., Kastner W., 1997, Thermal-Hydraulic Behavior of a PWR under Accident Conditions, Complementary Test Results from UPTF and PKL, NURETH-8 Conf., Kyoto (J)
Weiss F-P., Sawitzki M., Winkler F., 1986, UPTF, a full-scale PWR loss-of-coolant accident experiment program, J. Atomkern-Energie Kerntechnik, Vol. 49, 1-2
Umminger K., Kastner W., Liebert J., Mull T., 2001, Thermal hydraulics of PWRS with respect to boron dilution phenomena -Experimental results from the test facilities PKL and UPTF, J. Nuclear Engineering and Design, 204