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Author Kiril, Velkov ♦ Friederike, Bostelmann ♦ Winfried, Zwermann ♦ Alexander, Aures
Source Directory of Open Access Journals (DOAJ)
Content type Text
Publisher EDP Sciences
File Format PDF
Date Created 2016-03-17
Copyright Year ©2016
Language English
Subject Domain (in LCC) QC1-999
Subject Keyword Science ♦ Physics
Abstract Neutron transport and depletion calculations are performed in combination with various nuclear data libraries in order to assess the impact of nuclear data on safety-relevant parameters of sodium-cooled fast reactors. These calculations are supplemented by systematic uncertainty analyses with respect to nuclear data. Analysed quantities are the multiplication factor and nuclide densities as a function of burn-up and the Doppler and Na-void reactivity coefficients at begin of cycle. While ENDF/B-VII.0 / -VII.1 yield rather consistent results, larger discrepancies are observed between the JEFF libraries. While the newest evaluation, JEFF-3.2, agrees with the ENDF/B-VII libraries, the JEFF-3.1.2 library yields significant larger multiplication factors.
ISSN 2100014X
Age Range 18 to 22 years ♦ above 22 year
Educational Use Research
Education Level UG and PG ♦ Career/Technical Study
Learning Resource Type Article
Publisher Date 2016-01-01
e-ISSN 2100014X
Journal EPJ Web of Conferences
Volume Number 111
Starting Page 11003

Source: Directory of Open Access Journals (DOAJ)