کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
1730040 1521193 2008 4 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
On the performance of ENDF/B-VII.0 data for fast neutron fluence calculations
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
On the performance of ENDF/B-VII.0 data for fast neutron fluence calculations
چکیده انگلیسی

The newest release of the Evaluated Nuclear Data File, ENDF/B-VII.0, has recently become available, along with the announcement of its significant advances over previous versions. The older ENDF/B releases, however, have been assessed for numerous applications in the past and, as such, currently find wide application in the nuclear industry. An analysis of the influence of the recent upgrade in the data file is thus needed with respect to specific practical applications. The present technical note addresses the effects of modifications of the neutron cross-sections in the ENDF/B-VII.0 library, relative to the preceding ENDF/B-VI.8 release, on calculations of the fast neutron fluence accumulated in a PWR reactor pressure vessel, which is of direct relevance for the licensing and safe operation of nuclear power plants.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Annals of Nuclear Energy - Volume 35, Issue 12, December 2008, Pages 2432–2435
نویسندگان
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