کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
297104 511748 2013 9 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
3D core burnup studies in 500 MWe Indian prototype fast breeder reactor to attain enhanced core burnup
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
3D core burnup studies in 500 MWe Indian prototype fast breeder reactor to attain enhanced core burnup
چکیده انگلیسی

Fast breeder reactors are capable of producing high fuel burnup because of higher internal breeding of fissile material and lesser parasitic capture of neutrons in the core. As these reactors need high fissile enrichment, high fuel burnup is desirable to be cost effective and to reduce the load on fuel reprocessing and fabrication plants. A pool type, liquid sodium cooled, mixed (Pu–U) oxide fueled 500 MWe prototype fast breeder reactor (PFBR), under construction at Kalpakkam is designed for a peak burnup of 100 GWd/t. This limitation on burnup is purely due to metallurgical properties of structural materials like clad and hexcan to withstand high neutron fluence, and not by the limitation on the excess reactivity available in the core. The 3D core burnup studies performed earlier for approach to equilibrium core of PFBR is continued to demonstrate the burnup potential of existing PFBR core. To increase the fuel burnup of PFBR, plutonium oxide enrichment is increased from 20.7%/27.7% to 22.1%/29.4% of core-1/core-2 which resulted in cycle length increase from 180 to 250 effective full power days (efpd), so that the peak fuel burnup increases from 100 to 134 GWd/t, keeping all the core parameters under allowed safety limits. Number of diluents subassemblies is increased from eight to twelve at beginning of life core to bring down the initial core excess reactivity. PFBR refueling is revised to accommodate twelve diluents. Increase of 10B enrichment in control safety rods (CSRs) and diverse safety rods (DSRs) is made along with a design change in CSRs to increase the reactivity worth of absorber rods for ensuring safe reactor operation. This new enhanced burnup core can be used in the future with advanced structural materials for clad and hexcan, which can withstand higher neutron fluence and gamma radiation.


► Enhanced burnup potential of existing prototype fast breeder reactor core is studied.
► By increasing the Pu enrichment, fuel burnup can be increased in existing PFBR core.
► Enhanced burnup increase economy and reduce load of fuel fabrication and reprocessing.
► Beginning of life reactivity is suppressed by increasing the number of diluents.
► Absorber rod worth requirements can be achieved by increasing 10B enrichment.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Nuclear Engineering and Design - Volume 255, February 2013, Pages 359–367
نویسندگان
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