کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
1728892 1521153 2012 9 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Development of sub-channel code SACoS and its application in coupled neutronics/thermal hydraulics system for SCWR
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
Development of sub-channel code SACoS and its application in coupled neutronics/thermal hydraulics system for SCWR
چکیده انگلیسی

Supercritical Water Reactor (SCWR) is one of the promising reactors from the list of fourth generation of nuclear reactors. High thermal efficiency and low cost of electricity make it an attractive option in the era of growing energy demand. An almost seven fold density variation for coolant/moderator along the active height does not allow the use of constant density assumption for design calculations, as used for previous generations of reactors. The advancement in computer technology gives us the superior option of performing coupled analysis. Thermal hydraulics calculations of supercritical water systems present extra challenges as not many computational tools are available to perform that job. This paper introduces a new sub-channel code called Sub-channel Analysis Code of SCWR (SACoS) and its application in coupled analyses of High Performance Light Water Reactor (HPLWR). SACoS can compute the basic thermal hydraulic parameters needed for design studies of a supercritical water reactor. Multiple heat transfer and pressure drop correlations are incorporated in the code according to the flow regime. It has the additional capability of calculating the thermal hydraulic parameters of moderator flowing in water box and between fuel assemblies under co-current or counter current flow conditions. Using MCNP4c and SACoS, a coupled system has been developed for SCWR design analyses. The developed coupled system is verified by performing and comparing HPLWR calculations. The results were found to be in very good agreement. Significant difference between the results was seen when Doppler feedback effect was included in the coupled calculations. This difference is due to the use of different values of fuel temperature to include Doppler feedback in our and reference coupled systems. This also lays emphasis on the use of true representative values of critical parameters in the design calculations to get the real picture of conditions rather than over or under estimated values.


► A tool is developed for coupled neutronics/thermal-hydraulic analysis for SCWR.
► For thermal hydraulic analysis, a sub-channel code SACoS is developed and verified.
► Coupled analysis agree quite well with the reference calculations.
► Different choice of important parameters makes huge difference in design calculations.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Annals of Nuclear Energy - Volume 45, July 2012, Pages 37–45
نویسندگان
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