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contributor authorLindley, Ben
contributor authorÁlvarez Velarde, Francisco
contributor authorBaker, Una
contributor authorBodi, Janos
contributor authorCosgrove, Paul
contributor authorCharles, Alan
contributor authorFiorina, Carlo
contributor authorFridman, Emil
contributor authorKrepel, Jiri
contributor authorLavarenne, Jean
contributor authorMikityuk, Konstantin
contributor authorNikitin, Evgeny
contributor authorPonomarev, Alexander
contributor authorRadman, Stefan
contributor authorShwageraus, Eugene
date accessioned2023-11-29T19:34:27Z
date available2023-11-29T19:34:27Z
date copyright3/13/2023 12:00:00 AM
date issued3/13/2023 12:00:00 AM
date issued2023-03-13
identifier issn2332-8983
identifier otherners_009_03_031301.pdf
identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4294869
description abstractThe objective of this paper is to quantify the coupling effect on the power distribution of sodium-cooled fast reactors (SFRs), specifically the European SFR. Calculations are performed with several state-of-the-art reactor physics and Multiphysics codes (TRACE/PARCS, DYN3D, WIMS, COUNTHER, and GeN-Foam) to build confidence in the methodologies and validity of results. Standalone neutronic calculations were generally in excellent agreement with a reference Monte Carlo-calculated power distribution (from Serpent). Next, the impact of coolant density and fuel temperature Doppler feedback was calculated. Reactivity coefficients for perturbations in the inlet temperature, coolant heat up and core power was shown to be negative with values of around −0.5 pcm/°C, −0.3 pcm/°C, and −3.5 pcm/%, respectively. Fuel temperature and coolant density feedback was found to introduce a roughly −1%/+1% in/out power tilt across the core. Calculations were then extended to axial expansion for cases where fuel is linked and unlinked to the clad. Core calculations are in good agreement with each other. The impact of differential fuel expansion is found to be larger for fuel both linked and unlinked to the clad, with the in/out power tilt increasing to around −4%/+2%. Thus, while broadly confirming the known result that standalone physics calculations give good results, the expansion coupling effect is perhaps more than anticipated a priori. These results provide a useful benchmark for the further development of Multiphysics codes and methodologies in support of advanced reactor calculations.
publisherThe American Society of Mechanical Engineers (ASME)
titleImpact of Thermal-Hydraulic Feedback and Differential Thermal Expansion on European Sodium-Cooled Fast Reactor Core Power Distribution
typeJournal Paper
journal volume9
journal issue3
journal titleJournal of Nuclear Engineering and Radiation Science
identifier doi10.1115/1.4056930
journal fristpage31301-1
journal lastpage31301-13
page13
treeJournal of Nuclear Engineering and Radiation Science:;2023:;volume( 009 ):;issue: 003
contenttypeFulltext


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