کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
7964443 | 1514173 | 2016 | 11 صفحه PDF | دانلود رایگان |
عنوان انگلیسی مقاله ISI
Metallography and fuel cladding chemical interaction in fast flux test facility irradiated metallic U-10Zr MFF-3 and MFF-5 fuel pins
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کلمات کلیدی
WHCEFPDFCCIDFRIFRFMFBOLBOCEOCMFFPICTEBRPeaking factorbeginning of lifeBeginning Of Cycle - آغاز چرخهMOX - به زودیinductively coupled plasma mass spectrometry - طیفسنجی جرمی پلاسمای جفتشده القاییICP-MS - طیفسنجی جرمی پلاسمای جفتشده القاییFerritic-martensitic steel - فولاد مارتنزیتی فریتیMetallography - متالوگرافیPost-irradiation Examination - معاینه بعد از اشعهPie - پایEnd Of Cycle - پایان چرخه
موضوعات مرتبط
مهندسی و علوم پایه
مهندسی انرژی
انرژی هسته ای و مهندسی
پیش نمایش صفحه اول مقاله
![عکس صفحه اول مقاله: Metallography and fuel cladding chemical interaction in fast flux test facility irradiated metallic U-10Zr MFF-3 and MFF-5 fuel pins Metallography and fuel cladding chemical interaction in fast flux test facility irradiated metallic U-10Zr MFF-3 and MFF-5 fuel pins](/preview/png/7964443.png)
چکیده انگلیسی
The Mechanistic Fuel Failure (MFF) series of metal fuel irradiations conducted in the Fast Flux Test Facility (FFTF) provides an important comparison between data generated in the Experimental Breeder Reactor (EBR-II) and that expected in a larger-scale fast reactor. The MFF fuel operated with a peak cladding temperature at the top of the fuel column, but developed peak burnup at the centerline of the core. This places the peak fuel temperature midway between the core center and the top of fuel, lower in the fuel column than in EBR-II experiments. Data from the MFF-3 and MFF-5 assemblies are most comparable to the data obtained from the EBR-II X447 experiment. The two X447 pin breaches were strongly influenced by fuel/cladding chemical interaction (FCCI) at the top of the fuel column. Post irradiation examination data from MFF-3 and MFF-5 are presented and compared to historical EBR-II data.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Journal of Nuclear Materials - Volume 473, May 2016, Pages 167-177
Journal: Journal of Nuclear Materials - Volume 473, May 2016, Pages 167-177
نویسندگان
W.J. Carmack, H.M. Chichester, D.L. Porter, D.W. Wootan,