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dc.contributor.authorBurianová, Nicola
dc.contributor.authorKošt´ál, Michal
dc.contributor.authorSchulc, Martin
dc.contributor.authorŠimon, Jan
dc.contributor.authorMareček, Martin
dc.contributor.authorUhlíř, Jan
dc.date.accessioned2019-09-18T09:05:58Z
dc.date.available2019-09-18T09:05:58Z
dc.date.copyright4/16/2019 12:00:00 AM
dc.date.issued2019
dc.identifier.issn2332-8983
dc.identifier.otherners_005_03_030906
dc.identifier.urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4258843
dc.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%.
dc.publisherAmerican Society of Mechanical Engineers (ASME)
dc.titleMeasurement of Selected Differential Cross Sections in 235U Spectrum
dc.typeJournal Paper
dc.journal.volume5
dc.journal.issue3
dc.journal.titleJournal of Nuclear Engineering and Radiation Science
dc.identifier.doi10.1115/1.4042850
dc.journal.fristpage30906
dc.journal.lastpage030906-8
dc.treeJournal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 003
dc.contenttypeFulltext


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