کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
1727919 | 1521107 | 2016 | 9 صفحه PDF | دانلود رایگان |
عنوان انگلیسی مقاله ISI
Determination of the power density distribution in a PWR reactor based on neutron flux measurements at fixed reactor incore detectors
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کلمات کلیدی
موضوعات مرتبط
مهندسی و علوم پایه
مهندسی انرژی
مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
![عکس صفحه اول مقاله: Determination of the power density distribution in a PWR reactor based on neutron flux measurements at fixed reactor incore detectors Determination of the power density distribution in a PWR reactor based on neutron flux measurements at fixed reactor incore detectors](/preview/png/1727919.png)
چکیده انگلیسی
The proportionality between the neutron flux signal and the power density allows the determination of the linear power density at the detector location. Applying this property, it is shown in this paper the evolution of the power density monitoring methods, using neutron flux measurements in commercial reactors of the PWR type. For these measurements detectors positioned externally and internally to the reactor pressure vessel are used. As main task, this paper presents a calculation method that aims to determine the linear power density distribution in a PWR, in 3D, based on the measurements at fixed neutron detector positions in the reactor core. The power densities measured at the detectors locations in the reactor core, are used to correct the power densities, which were calculated from design data. Accordingly, the neutron flux is corrected for all other regions of the reactor core and a new power density distribution is determined. To evaluate the obtained power distribution, this procedure was applied for the beginning of cycle-1 of a commercial PWR of 3765Â MWth. This calculated power distribution was compared to the power distribution measured using the neutron flux mapping performed with the aeroball system, which consists of indirect measurements of the neutron flux through probe activation in axial and radial positions of the reactor core. The observed differences resulted in a standard deviation of less than 3% and a maximum deviation less than 5%.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Annals of Nuclear Energy - Volume 90, April 2016, Pages 148-156
Journal: Annals of Nuclear Energy - Volume 90, April 2016, Pages 148-156
نویسندگان
A.M. Dias, F.C. Silva,