کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
1729282 1521165 2011 6 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Contributions to the neutronic analysis of a gas-cooled fast reactor
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
Contributions to the neutronic analysis of a gas-cooled fast reactor
چکیده انگلیسی

In this work the Monte Carlo codes MCNPX and TRIPOLI-4 were used to perform the criticality calculations of the fuel assembly and the core configuration of a gas-cooled fast reactor (GFR) concept, currently in development. The objective is to make contributions to the neutronic analysis of a gas-cooled fast reactor. In this study the fuel assembly is based on a hexagonal lattice of fuel-pins. The materials used are uranium and plutonium carbide as fuel, silicon carbide as cladding, and helium gas as coolant. Criticality calculations were done for a fuel assembly where the axial reflector thickness was varied in order to find the optimal thickness. In order to determine the best material to be used as a reflector, in the reactor core with neutrons of high energy spectrum, criticality calculations were done for three reflector materials: zirconium carbide, silicon carbide and natural uranium. It was found that the zirconium carbide provides the best neutron reflection. Criticality calculations using different active heights were done to determine the optimal height, and the reflector thickness was adjusted. Core criticality calculations were performed with different radius sizes to determine the active radial dimension of the core. A negative temperature coefficient of reactivity was verified for the fuel. The effect on reactivity produced by changes in the coolant density was also evaluated. We present the main neutronic characteristics of a preliminary fuel and core designs for the GFR concept. ENDF-VI cross-sections libraries were used in both the MCNPX and TRIPOLI-4 codes, and we verified that the obtained results are very similar.


► Differences on reactivity with MCNPX and TRIPOLI-4 are negligible.
► Fuel lattice and core criticality calculations were done.
► A higher Doppler coefficient than coolant density coefficient.
► Zirconium carbide is a better reflector than silicon carbide.
► Adequate active height, radial size and reflector thickness were obtained.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Annals of Nuclear Energy - Volume 38, Issue 6, June 2011, Pages 1406–1411
نویسندگان
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