Benchmarking of stainless steel cube neutron leakage in Research Center Rez

TL;DR

This paper presents benchmarking of neutron leakage from a stainless steel cube using experimental measurements and uncertainty analysis to validate transport cross section data, aiding in nuclear data validation efforts.

Contribution

It provides a comprehensive validation of neutron leakage data from a stainless steel cube through combined experimental and uncertainty analysis, enhancing nuclear data validation methods.

Findings

Consistent results between stilbene spectrometry and activation measurements.

Identification and evaluation of main sources of uncertainty.

Validation supports the use of simple geometric assemblies for neutron leakage studies.

Abstract

The integral experiments covering the neutron leakage from geometrically simple assemblies with a 252Cf source inside are very valuable tools usable in validation of transport cross section data, since geometric uncertainties play a much smaller role in simple geometric assemblies than in complex assemblies as for example reactor pressure vessel geometry. Since 252Cf(s.f.) is standard neutron source, the uncertainties connected with the source neutron spectrum can be even neglected. The paper refers on validation efforts of neutron leakage from stainless steel block ~50 x 50 x50 cm in Research Center Rez. Both the neutron leakage flux at a distance of 1 m from the center of the cubical assembly using stilbene spectrometry and the activation rates at different positions of the assembly were evaluated. In addition to experiments, main sources of uncertainty were identified and evaluated. The results of the stilbene measurements are consistent with the activation measurements results.