The Application of Silicon-Filtered Beam in the Validation of Iron Cross Sections by Deep Penetration Experiments

Author:

Juříček Vlastimil1,Košťál Michal2,Losa Evžen2,Czakoj Tomáš2,Matěj Zdeněk3,Cvachovec František4,Schulc Martin2,Šimon Jan2,Mravec Filip3,Přenosil Václav3,Rypar Vojtěch2

Affiliation:

1. Department of LR-0 Reactor Operations, Research Centre Rez, 250 68, Husinec-Řež 130, Czech Republic

2. Department of Reactor Physics, Research Centre Rez, 250 68, Husinec-Řež 130, Czech Republic

3. Faculty of Informatics, Masaryk University, Botanická 15, Brno 612 00, Czech Republic

4. Department of Mathematics and Physics, University of Defence, Kounicova 65, Brno 612 00, Czech Republic

Abstract

Abstract This paper summarizes the issue of the validation of the silicon-filtered neutron beam transport in the deep neutron transport penetration experiment in iron. Iron is an essential structural material important for nuclear technology. The use of a silicon-filtered beam is a very interesting method because some significant peaks occur in the spectrum, helping to study selected wide energy regions during the deep neutron transport in the iron. The detailed characterization of the silicon-filtered beam has been performed in the past as well. Therefore, the input spectrum for the penetration experiments is well-known. The character of the input spectrum is reflecting the fine structure of the silicon cross section in region 1–8 MeV. Based on the agreement between calculated and measured attenuation in groups located within the neutron flux peaks, one can reveal possible problems in neutron transport description. The results are confirming satisfactory agreement of neutron transport description in ENDF/B-VII.1 in the majority of energy regions, while in the interval 4.7–6 MeV, underprediction in attenuation can be observed. This seems to be a consequence of discrepancies in the angular distribution of scattered neutrons. These results constitute an advance to previously performed integral experiments characterizing the neutron transport in iron using 252Cf(s.f) and 235U(nth;fiss).

Publisher

ASME International

Subject

Nuclear Energy and Engineering,Radiation

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