کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
8068857 | 1521118 | 2015 | 7 صفحه PDF | دانلود رایگان |
عنوان انگلیسی مقاله ISI
Uncertainty analysis of delayed neutron fissile material assay using a genetic algorithm
ترجمه فارسی عنوان
تجزیه و تحلیل عدم قطعیت از تأخیر در تجزیه مواد ناپایدار با استفاده از یک الگوریتم ژنتیکی
دانلود مقاله + سفارش ترجمه
دانلود مقاله ISI انگلیسی
رایگان برای ایرانیان
کلمات کلیدی
آزمایش غیر مخرب، الگوریتم ژنتیک، نوترون تاخیر تجزیه و تحلیل عدم قطعیت،
موضوعات مرتبط
مهندسی و علوم پایه
مهندسی انرژی
مهندسی انرژی و فناوری های برق
چکیده انگلیسی
An uncertainty analysis of non-destructive assay of spent fuel using a delayed neutron method was conducted to explicitly define the accuracy with which plutonium content in an uncharacterized sample can be assessed. Perturbing various parameters allowed for an investigation of the sensitivity of this method to various nuclear data, and it was determined that the relative delayed neutron group abundances had the largest effect on the genetic algorithm. Specifically, for a sample containing 235U, 238U, and 239Pu, irradiations in the thermal spectrum were shown to be more sensitive to 235U and 239U data, while irradiations in a fast spectrum were shown to be more sensitive to the 238U data. The overall uncertainties of the mass estimates were 15%, 5%, and 30% for 235U, 238U, and 239Pu, respectively. Finally, reducing the first delayed neutron group abundances by a factor of three as suggested by recent research reduced the overall uncertainties to 10%, 3%, and 20%.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Annals of Nuclear Energy - Volume 80, June 2015, Pages 460-466
Journal: Annals of Nuclear Energy - Volume 80, June 2015, Pages 460-466
نویسندگان
Ryan P. Kelley, Lucas M. Rolison, Dominik Raetz, Kelly A. Jordan,