Challenges in coupled thermal–hydraulics and neutronics simulations for LWR safety analysis

Ivanov, Kostadin; Avramova, Maria

doi:10.1016/j.anucene.2007.02.016

Cited by 71 publications

(19 citation statements)

References 7 publications

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“…It was shown before in previous studies 89 Figure 9A-C shows the convergence of the neutronic and thermal-hydraulic parameters for few coupling iterations. TRACE is executed first with uniform axial power in all nodes.…”

Section: Application 2: Multiphysics Couplingsupporting

confidence: 73%

Combining simulations and data with deep learning and uncertainty quantification for advanced energy modeling

Radaideh

Kozłowski

2019

Int J Energy Res

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Summary A novel and modern framework for energy modeling is developed in this paper with a focus on nuclear energy modeling and simulation. The framework combines multiphysics simulations and real data, with validation by uncertainty quantification tasks and facilitation by machine and deep learning methods. The hybrid framework is built on the basis of a wide range of physical models, real data, mathematical and statistical methods, and artificial intelligence techniques. The framework is demonstrated in different applications, including quantifying uncertainties in computer simulations, multiphysics coupling, analysis of variance using machine learning surrogate models, deep learning of time series phenomena, and propagating parametric uncertainties of nuclear data. The applications demonstrated are oriented to nuclear engineering simulations, even though majority of the methods are applicable to other energy sources (eg, renewable). Efficient utilization of this framework is expected to yield a much better understanding of the physical phenomena analyzed as well as an improvement in the performance of the energy design/model under construction.

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Section: Application 2: Multiphysics Couplingsupporting

confidence: 73%

Combining simulations and data with deep learning and uncertainty quantification for advanced energy modeling

Radaideh

Kozłowski

2019

Int J Energy Res

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“…Some codes utilizes the methodologies for point kinetics model such that several parallel coolant channel and corresponding fuel rod models describing the parts of the reactor core in such a way as to utilizes the boundary conditions at the core inlet and outlet supplied by the system code .This method can be expanded to full 3D model and coupled to thermal hydraulic model and heat structure model in the core region. [5] Figure. The coupling between thermal hydraulic and neutronics can be performed in two ways i.e internal and external with advantages and deficiencies are lied upon.…”

Section: Neutronic Modelmentioning

confidence: 99%

Neutronics and Thermal Hydraulic Coupling Methods for the Nuclear Reactor Core

Ud-Din¹,

Peng²,

Zubair³

2011

2011 Asia-Pacific Power and Energy Engineering Conference

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In this paper an overview of the coupling methodologies between reactor physics (Neutronics) and thermal hydraulic have been studied by taken into account the previous and ongoing research. The current study includes the neutronics and thermal hydraulic model and the coupling methodology between the two phenomenons which is inter related with computational approach. Since the coupling involves some computer codes which exchanges the data between the neutronics and thermal hydraulic so in this paper possible computer codes are also have been listed with their categories. Finally the advantages of the coupling are described with some suggestions and conclusion is also given.

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“…Verification of this coupled technique was done by Jackson et al . for the core transient analysis .ATHLETE code coupled with 3D core neutronic model DYN3D has been used for the analysis of BWR Turbine trip benchmark, and the validation of this code for PWR and BWR was done by Glaeser .Similarly, the code like ATHLET‐QUABOX/CUBBOX has been used by Langenbuch for the analysis of OECD/NRC BWR Turbine trip benchmark .RELAP code has been coupled with point kinetic codes for the analysis of OECD/NEA PWR MSLB by Sanchez‐Espanioza and Nigro et al . .CATHORE code has been coupled with CRONOS2‐FLICA4 for BWR turbine trip analysis .…”

Section: Introductionmentioning

confidence: 99%

Neutronics and thermal hydraulic coupling analysis of integrated pressurized water reactor

Khan

Peng

Khan

2012

Int. J. Energy Res.

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In this paper, three-dimensional (3D) power distribution of newly designed small nuclear reactor core has been achieved by using neutron kinetic/thermal hydraulic (NK/TH) coupling. This is pressurized water reactor-based small nuclear reactor in which plate type fuel element has been used and the core of the reactor has hexagonal type geometry. This paper depicts the design of the reactor core by using coupling approach of neutronics(Neutron Kinetic) and thermal hydraulic studies. For this purpose, neutronic analysis has been obtained by using lattice physics code, i.e. HELIOS and neutron kinetic code, i.e. REMARK. HELIOS code gives the cross-section data which is being used as input to the REMARK code. At the same time, THEATRe code was used for the thermal hydraulic analysis of the reactor core. In the coupling process, some data (fuel temperature, moderator temperature, void fraction, etc.) from THEATRe code has been used in conjunction with HELIOS and REMARK codes. After finalizing the NK/TH coupling, 3D evaluation of the power distribution of the reactor core has been achieved and is included in the paper. The purpose of this paper is to evaluate the design and get the normal operational behavior of the reactor core by NK/TH coupling approach.

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Challenges in coupled thermal–hydraulics and neutronics simulations for LWR safety analysis

Cited by 71 publications

References 7 publications

Combining simulations and data with deep learning and uncertainty quantification for advanced energy modeling

Combining simulations and data with deep learning and uncertainty quantification for advanced energy modeling

Neutronics and Thermal Hydraulic Coupling Methods for the Nuclear Reactor Core

Neutronics and thermal hydraulic coupling analysis of integrated pressurized water reactor

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