National Repository of Grey Literature 3 records found  Search took 0.01 seconds. 
Cross section measurement in reactor spectrum: 55Mn(n,2n), 90Zr(n,2n), 127I(n,2n)
Burianová, Nicola ; Košťál, Michal (advisor) ; Krtička, Milan (referee)
This diploma thesis deals with the validation of spectral average cross-sections (SACS) of 55 Mn(n,2n)54 Mn, 90 Zr(n,2n)89 Zr, 127 I(n,2n)126 I reactions in well-defined LR-0 reactor spectrum. The measurement of SACS for selected reactions is of high interest because they are used for the practical reactor dosimetry. Various experiments for description of neutron field in reactor and detector characterization, which are necessary for validation, are described. The spectral average cross-sections are derived from Net Peak Areas of irradiated samples measured using a semiconductor high purity germanium detector. Obtained result were compared with MCNP6 calculations using ENDF/B-VII.0, ENDF/B-VII.1, JEFF-3.1, JEFF-3.2, JENDL-3.3, JENDL-4, ROSFOND-2010, CENDL-3.1 and IRDFF nuclear data libraries. Notable discrepancies were found in 90 Zr(n,2n)89 Zr and 127 I(n,2n)126 I reactions. This thesis also contains a theoretical basis for the interaction of neutrons with matter.
Cross section measurement in reactor spectrum: 55Mn(n,2n), 90Zr(n,2n), 127I(n,2n)
Burianová, Nicola ; Košťál, Michal (advisor) ; Krtička, Milan (referee)
This diploma thesis deals with the validation of spectral average cross-sections (SACS) of 55 Mn(n,2n)54 Mn, 90 Zr(n,2n)89 Zr, 127 I(n,2n)126 I reactions in well-defined LR-0 reactor spectrum. The measurement of SACS for selected reactions is of high interest because they are used for the practical reactor dosimetry. Various experiments for description of neutron field in reactor and detector characterization, which are necessary for validation, are described. The spectral average cross-sections are derived from Net Peak Areas of irradiated samples measured using a semiconductor high purity germanium detector. Obtained result were compared with MCNP6 calculations using ENDF/B-VII.0, ENDF/B-VII.1, JEFF-3.1, JEFF-3.2, JENDL-3.3, JENDL-4, ROSFOND-2010, CENDL-3.1 and IRDFF nuclear data libraries. Notable discrepancies were found in 90 Zr(n,2n)89 Zr and 127 I(n,2n)126 I reactions. This thesis also contains a theoretical basis for the interaction of neutrons with matter.
Measurement of output distribution in LR-0 experimental reactor core (Research Centre Rez) using a semiconductor gamma-spectrometry
BRABCOVÁ, Jitka
The objective of the present work is to study the theoretical and practical background of the measurement of output distribution in LR-0 experimental reactor core (Research Center Rez) by means of neutron activation method and by means of fuel rods scanning using a semiconductor gamma-spectrometry. In the practical part of the work, axial and radial distributions of reaction rate in the vicinity of the centre of reactor core were measured. Further, axial distribution of the activity of the fission product 140La in a fuel rod from LR-0 was estimated.

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