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contributor authorBurianová, Nicola
contributor authorKošt´ál, Michal
contributor authorSchulc, Martin
contributor authorŠimon, Jan
contributor authorMareček, Martin
contributor authorUhlíř, Jan
date accessioned2019-09-18T09:05:58Z
date available2019-09-18T09:05:58Z
date copyright4/16/2019 12:00:00 AM
date issued2019
identifier issn2332-8983
identifier otherners_005_03_030906
identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4258843
description abstractThis paper describes the measurement of 55Mn(n,2n) and 127I(n,2n) reaction rates in a well-defined reactor field in a special core of LR-0 reactor. The reaction rates were derived using gamma-spectrometry by measuring gamma activities of irradiated MnO2 and NaI samples at a high purity germanium (HPGe) detector. The spectral average cross section (SACS) in 235U prompt fission neutron spectrum (PFNS) was experimentally determined to be 0.2393 ± 0.015 × 10−3 b for 55Mn and 1.2087 ± 0.052 × 10−3 b for 127I. These obtained results were compared with calculations by MCNP6 code using ENDF/B VII.1, ENDF/B VII, JEFF-3.1, JEFF-3.2, JENDL-3.3, JENDL-4, ROSFOND- 2010, CENDL-3.1, and IRDFF nuclear data libraries. In a case of 55Mn, a good agreement with ENDF/B VII.1, JEFF 3.1, JENDL 3.3, JENDL 4, ROSFOND, and CENDL 3.1 nuclear data libraries was found, where C/E−1 is 0.1%, while IRDFF underestimated by about 15.8%. In the case of 127I, more significant discrepancies were found, where JENDL 3.3 and JENDL 4 overestimate the result by about 31.3%.
publisherAmerican Society of Mechanical Engineers (ASME)
titleMeasurement of Selected Differential Cross Sections in 235U Spectrum
typeJournal Paper
journal volume5
journal issue3
journal titleJournal of Nuclear Engineering and Radiation Science
identifier doi10.1115/1.4042850
journal fristpage30906
journal lastpage030906-8
treeJournal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 003
contenttypeFulltext


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