Void Reactivity Coefficient Analysis during Void Fraction Changes in Innovative BWR Assemblies

Slavickas, Andrius; Pabarčius, Raimondas; Tonkunas, A.; Stankūnas, Gediminas; Ušpuras, E.

doi:10.1155/2015/757201

Cited by 3 publications

(2 citation statements)

References 10 publications

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“…e decomposition analysis of the neutron multiplication factor, being an extremely useful instrument and quantitative testing measure [14], was employed in this study with the objective to explain the discrepancies in simulation results. e reactivity differences between simulation cases were decomposed to separate components, which represent the contributions of the separate region to the total reactivity difference.…”

Section: E Influence Of User-defined Dfsmentioning

confidence: 99%

Neutron Transport Simulations of RBMK Fuel Assembly Using Multigroup and Continuous Energy Data Libraries within the SCALE Code

Slavickas

Pabarčius

Tonkunas

et al. 2021

Science and Technology of Nuclear Installations

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The neutron transport simulations of RBMK-1500 fuel assembly were performed using both multigroup and continuous energy data libraries available within the SCALE code system in order to validate its suitability for the estimation of RBMK neutronic characteristics. The resonance processing of cross section, involved in the preparation of the multigroup data library, has a significant impact on neutron transport calculations. Standard Dancoff factors (DFs) used for the heterogeneous geometry of RBMK fuel assembly are insufficient for the accurate estimation of resonance self-shielding. Thus, the SCALE module MCDancoff was used in this study to determine location-specific DFs. The results of RBMK-1500 fuel assembly simulations using standard and user-defined DFs were compared. In addition, the continuous energy (CE) cross-section data library was applied for the benchmark calculations. The impact of different nuclear data libraries on neutron transport simulations was tested as well. It was found out that the usage of the multigroup data libraries generates some deviation from the reference simulations obtained with CE libraries. The CE library based on the estimated ENDF/B-VII.1 data proved to be the best alternative for neutron transport simulations of RBMK fuel assembly.

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Section: E Influence Of User-defined Dfsmentioning

confidence: 99%

Neutron Transport Simulations of RBMK Fuel Assembly Using Multigroup and Continuous Energy Data Libraries within the SCALE Code

Slavickas

Pabarčius

Tonkunas

et al. 2021

Science and Technology of Nuclear Installations

Self Cite

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show abstract

“…However, the question is whether this effect can be estimated accurately by employing 2D model and using the average coolant density. The analysis presented in this paper is a continuation of the work on study of void reactivity coefficient in innovative BWR fuel assemblies [5]. The investigation of the void reactivity variation using deterministic T-NEWT functional module of SCALE package in the entire 0-100% void fraction range was performed in the previous study.…”

Section: Introductionmentioning

confidence: 99%

Analysis of Void Reactivity Coefficient for 3D BWR Assembly Model

Slavickas¹,

Pabarčius²,

Tonkunas³

et al. 2016

Science and Technology of Nuclear Installations

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The effect of BWR fuel assembly 3D model on void reactivity coefficient (VRC) estimation is investigated. VRC values were calculated for different BWR assembly models applying deterministic T-NEWT and Monte Carlo KENO-VI functional modules of SCALE 6.1 code package. The difference between deterministic T-NEWT and Monte Carlo KENO-VI simulations is negligible (0.18 pcm/%). The influence of the assumed more detailed coolant density profile was estimated as well. VRC increases with the application of a larger number of coolant density values across fuel assembly height. It was shown that the coolant density profile described by 6 values per height could be considered sufficient from prospect of VRC estimation, as a more detailed density profile has impact below 1% on total assembly void effects. VRC values were decomposed to values for individual nodes and isotopes, since decomposition provides useful insights to describe the overall behaviour of VRC in detail.

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New 4D and 3D models of chaotic systems developed from the dynamic behavior of nuclear reactors

Ablay

2022

Chaos: An Interdisciplinary Journal of Nonlinear Science

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The complex, highly nonlinear dynamic behavior of nuclear reactors can be captured qualitatively by novel four-dimensional (that is, fourth order) and three-dimensional (that is, third order) models of chaotic systems and analyzed with Lyapunov spectra, bifurcation diagrams, and phase diagrams. The chaotic systems exhibit a rich variety of bifurcation phenomena, including the periodic-doubling route to chaos, reverse bifurcations, anti-monotonicity, and merging chaos. The offset boosting method, which relocates the attractor’s basin of attraction in any direction, is demonstrated in these chaotic systems. Both constant parameters and periodic functions are seen in offset boosting phenomena, yielding chaotic attractors with controlled mean values and coexisting attractors.

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Void Reactivity Coefficient Analysis during Void Fraction Changes in Innovative BWR Assemblies

Cited by 3 publications

References 10 publications

Neutron Transport Simulations of RBMK Fuel Assembly Using Multigroup and Continuous Energy Data Libraries within the SCALE Code

Neutron Transport Simulations of RBMK Fuel Assembly Using Multigroup and Continuous Energy Data Libraries within the SCALE Code

Analysis of Void Reactivity Coefficient for 3D BWR Assembly Model

New 4D and 3D models of chaotic systems developed from the dynamic behavior of nuclear reactors

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