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The integral experiments covering the neutron leakage from geometricallysimple assemblies with a 252Cf source inside are very valuable tools usable invalidation of transport cross section data, since geometric uncertainties playa much smaller role in simple geometric assemblies than in complex assembliesas for example reactor pressure vessel geometry. Since 252Cf(s.f.) is standardneutron source, the uncertainties connected with the source neutron spectrumcan be even neglected. The paper refers on validation efforts of neutronleakage from stainless steel block ~50 x 50 x50 cm in Research Center Rez. Boththe neutron leakage flux at a distance of 1 m from the center of the cubicalassembly using stilbene spectrometry and the activation rates at differentpositions of the assembly were evaluated. In addition to experiments, mainsources of uncertainty were identified and evaluated. The results of thestilbene measurements are consistent with the activation measurements results.

Benchmarking of stainless steel cube neutron leakage in Research Center Rez