Cross Section Influence on Monte Carlo Based Burn Up Codes Applied to a GFR Like ConfigurationSource: Journal of Nuclear Engineering and Radiation Science:;2015:;volume( 001 ):;issue: 003::page 31004DOI: 10.1115/1.4029521Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: This paper reports the results of a comparison among JEFF and ENDF/B data sets when used by SERPENT and MONTEBURNS codes on a gascooled fast reactor (GFR)like configuration. Particularly, it shows a comparison between the two Monte Carlobased codes, each one adopting three different crosssection data sets, namely, JEFF3.1, JEFF3.1.2, and ENDF/BVII.1. Calculations have been carried out on the Allegro reactor, i.e.,آ an experimental GFRlike facility that could be built in the European Union as a GFR demonstration. Results include nuclear parameters, such as the effective multiplication factor and fluxes, as well as the atomic densities for some important nuclides versus burnup.
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| contributor author | Chersola, Davide | |
| contributor author | Lomonaco, Guglielmo | |
| contributor author | Mazzini, Guido | |
| date accessioned | 2017-05-09T01:22:22Z | |
| date available | 2017-05-09T01:22:22Z | |
| date issued | 2015 | |
| identifier issn | 2332-8983 | |
| identifier other | NERS_1_3_031004.pdf | |
| identifier uri | http://yetl.yabesh.ir/yetl/handle/yetl/159302 | |
| description abstract | This paper reports the results of a comparison among JEFF and ENDF/B data sets when used by SERPENT and MONTEBURNS codes on a gascooled fast reactor (GFR)like configuration. Particularly, it shows a comparison between the two Monte Carlobased codes, each one adopting three different crosssection data sets, namely, JEFF3.1, JEFF3.1.2, and ENDF/BVII.1. Calculations have been carried out on the Allegro reactor, i.e.,آ an experimental GFRlike facility that could be built in the European Union as a GFR demonstration. Results include nuclear parameters, such as the effective multiplication factor and fluxes, as well as the atomic densities for some important nuclides versus burnup. | |
| publisher | The American Society of Mechanical Engineers (ASME) | |
| title | Cross Section Influence on Monte Carlo Based Burn Up Codes Applied to a GFR Like Configuration | |
| type | Journal Paper | |
| journal volume | 1 | |
| journal issue | 3 | |
| journal title | Journal of Nuclear Engineering and Radiation Science | |
| identifier doi | 10.1115/1.4029521 | |
| journal fristpage | 31004 | |
| journal lastpage | 31004 | |
| tree | Journal of Nuclear Engineering and Radiation Science:;2015:;volume( 001 ):;issue: 003 | |
| contenttype | Fulltext |