کد مقاله کد نشریه سال انتشار مقاله انگلیسی ترجمه فارسی نسخه تمام متن
4925268 1363149 2017 5 صفحه PDF سفارش دهید دانلود کنید
عنوان انگلیسی مقاله
Fissile worth of MOX fuel: A non destructive study
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
Fissile worth of MOX fuel: A non destructive study
چکیده انگلیسی
Quality of (U,Pu)O2 mixed oxide (MOX) fuels for fast reactor is judged by its fissile worth; quantified as Pu239 equivalence which is governed by the isotopic composition of PuO2 used for fuel fabrication and the concentration of PuO2. An experimental method for directly estimating Pu239 equivalence of MOX fuel pins for the upcoming Prototype Fast Breeder Reactor (PFBR) was attempted using passive gamma scanning (PGS) in this work. A combination method of theoretical and experimental estimations was used to study the dependence of deterioration in fissile worth of stored fuel pins with corresponding change in their PGS responses. This is a novel and effective method to estimate the updated value of fissile worth at the time of reactor loading after long duration of storage after fabrication of fuel pins.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Nuclear Engineering and Design - Volume 325, 15 December 2017, Pages 124-128
نویسندگان
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