This paper deals with the establishment of uncertainty ranges for sing
le valued parameters based on the analysis of four counterpart tests,
i. e., similar tests performed in differently scaled pressurized water
reactor simulators. A statistical method was developed to interpret t
he distribution of single valued parameters which are relevant in the
transient. The test consists Of a small break loss-of-coolant accident
caused by a roughly 6 % break in the cold leg. The test was performed
in the facilities LOBI, SPES, BETHSY and LSTF. The code RELAP5/MOD2 w
as used to predict the test scenarios. This work is part of a wide-ran
ging research on the evaluation of the scaling capabilities of system
thermal-hydraulic codes.