Superphénix Benchmark Part I: Results of Static NeutronicsSource: Journal of Nuclear Engineering and Radiation Science:;2021:;volume( 008 ):;issue: 001::page 11320-1Author:Ponomarev, Alexander
,
Mikityuk, Konstantin
,
Zhang, Liang
,
Nikitin, Evgeny
,
Fridman, Emil
,
Álvarez-Velarde, Francisco
,
Romojaro Otero, Pablo
,
Jiménez-Carrascosa, Antonio
,
García-Herranz, Nuria
,
Lindley, Ben
,
Baker, Una
,
Seubert, Armin
,
Henry, Romain
DOI: 10.1115/1.4051449Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: In the paper, the specification of a new neutronics benchmark for large sodium cooled fast reactor (SFR) core and results of modeling by different participants are presented. The neutronics benchmark describes the core of the French sodium cooled reactor Superphénix at its startup configuration, which in particular was used for experimental measurement of reactivity characteristics. The benchmark consists of the detailed heterogeneous core specification for neutronic analysis and the results of the reference solution. Different core geometries and thermal conditions from the cold “as fabricated” up to full power were considered. The reference Monte Carlo (MC) solution of serpent 2 includes data on multiplication factor, power distribution, axial and radial reaction rates distribution, reactivity coefficients and safety characteristics, control rods worth, kinetic data. The results of modeling with seven other solutions using deterministic and MC methods are also presented and compared to the reference solution. The comparisons results demonstrate appropriate agreement of evaluated characteristics. The neutronics results will be used in the second phase of the benchmark for the evaluation of transient behavior of the core.
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contributor author | Ponomarev, Alexander | |
contributor author | Mikityuk, Konstantin | |
contributor author | Zhang, Liang | |
contributor author | Nikitin, Evgeny | |
contributor author | Fridman, Emil | |
contributor author | Álvarez-Velarde, Francisco | |
contributor author | Romojaro Otero, Pablo | |
contributor author | Jiménez-Carrascosa, Antonio | |
contributor author | García-Herranz, Nuria | |
contributor author | Lindley, Ben | |
contributor author | Baker, Una | |
contributor author | Seubert, Armin | |
contributor author | Henry, Romain | |
date accessioned | 2022-05-08T08:30:22Z | |
date available | 2022-05-08T08:30:22Z | |
date copyright | 10/8/2021 12:00:00 AM | |
date issued | 2021 | |
identifier issn | 2332-8983 | |
identifier other | ners_008_01_011320.pdf | |
identifier uri | http://yetl.yabesh.ir/yetl1/handle/yetl/4284012 | |
description abstract | In the paper, the specification of a new neutronics benchmark for large sodium cooled fast reactor (SFR) core and results of modeling by different participants are presented. The neutronics benchmark describes the core of the French sodium cooled reactor Superphénix at its startup configuration, which in particular was used for experimental measurement of reactivity characteristics. The benchmark consists of the detailed heterogeneous core specification for neutronic analysis and the results of the reference solution. Different core geometries and thermal conditions from the cold “as fabricated” up to full power were considered. The reference Monte Carlo (MC) solution of serpent 2 includes data on multiplication factor, power distribution, axial and radial reaction rates distribution, reactivity coefficients and safety characteristics, control rods worth, kinetic data. The results of modeling with seven other solutions using deterministic and MC methods are also presented and compared to the reference solution. The comparisons results demonstrate appropriate agreement of evaluated characteristics. The neutronics results will be used in the second phase of the benchmark for the evaluation of transient behavior of the core. | |
publisher | The American Society of Mechanical Engineers (ASME) | |
title | Superphénix Benchmark Part I: Results of Static Neutronics | |
type | Journal Paper | |
journal volume | 8 | |
journal issue | 1 | |
journal title | Journal of Nuclear Engineering and Radiation Science | |
identifier doi | 10.1115/1.4051449 | |
journal fristpage | 11320-1 | |
journal lastpage | 11320-25 | |
page | 25 | |
tree | Journal of Nuclear Engineering and Radiation Science:;2021:;volume( 008 ):;issue: 001 | |
contenttype | Fulltext |