Development of a coupled neutronic/thermal-hydraulic tool with multi-scale capabilities and applications to HPLWR core analysis

Monti, L.; Starflinger, Jörg; Schulenberg, Thomas S.

doi:10.1016/j.nucengdes.2011.02.012

Cited by 15 publications

(3 citation statements)

References 14 publications

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“…Heat Transfer Calculation Model. One-dimensional model with radial heat conduction and convective heat transfer is used for hear transfer calculation [9], which is shown as equation (3).…”

Section: Research Objectmentioning

confidence: 99%

Influence Analysis of Coupled Neutronics and Thermo-Hydraulics on Steady-State Characteristics of Supercritical Water-Cooled Reactor

Chen

Zhou

Hou

et al. 2012

AMR

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the coulped neutronics and thermo-hydraulics model for supercritical water-cooled reactor (SCWR) is developed by internal coupling method. It is based on the two group neutron diffusion equations and the one-dimensional junction thermal analysis mode, in which the cross sections used for SCWR are generated by Dragon tool. Compared with the calculation results based on the non-coupling calculation model, the steady state characteristics under coupling calculation condition are detailed analyzed by considering parameters feedback at each axial node. The results show that, as coupled model is chosen its axial power distribution would give an obvious deviation from the cosine function that used for non-coupled model. Although the cladding temperature at most of the axial nodes rises with a shifted power peak, the maximum cladding temperature is finally decreased. For the above coupling condition, the maximum cladding temperature would appear at the external assemblies with lower coolant temperature but not at inner assemblies with higher coolant temperature. As the detailed description for coupling characteristics of supercritical water-cooled reactor is given, a certain theory reference for its system safety could be provided.

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“…Heat Transfer Calculation Model. One-dimensional model with radial heat conduction and convective heat transfer is used for hear transfer calculation [9], which is shown as equation (3).…”

Section: Research Objectmentioning

confidence: 99%

Influence Analysis of Coupled Neutronics and Thermo-Hydraulics on Steady-State Characteristics of Supercritical Water-Cooled Reactor

Chen

Zhou

Hou

et al. 2012

AMR

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“…Chauliac et al explained the European Reference Simulation Platform for Nuclear Reactors (NURESIM) is introduced where the reference platform shows some the software, modeling, and common analyses [15]. Monti et al worked that the core design is performed with neutronic and thermal-hydraulic analyses for the descriptions for the power and coolant behaviors [16]. Liu et al worked that the safety feature was analyzed with the SIMMER-III code for heavy liquid metal cooled reactors [17].…”

Section: Introductionmentioning

confidence: 99%

Modeling of Technology Evolution (TE) for Nuclear Industry in Aspect of Multidisciplinary R&Ds

Woo¹

2022

IJETAE

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Technology platform (TP) is introduced for the nuclear industrial promotions in the aspect of the inerdisplinary technology. The modeling is assumed as the introduction in 2010 which has been a role of the TP in the nuclear industry. The evolution of the new TP is one of important strategy to enhance the profits of the nuclear energy industry. Conventional trends of R&Ds as discovery and invention have been changed to the platform supplies which are incorporated with the information technology (IT) company. In the modeling, the multidisciplinary R&Ds can imply new TP in which the simulation is quantified and then the comparative values are obtained. The analysis performed by the technology evolution (TE) has been done for the dynamical simulations where the other kinds of TP could be expected. Keywords—Technology Platform (TP), Nuclear Energy, Industry, Information Technology (IT), Technology Evolution (TE)

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“…However, the matrix could be excessively large and encounter numerical challenges. Currently, LC methods are used to solve complex nuclear reactor problems (Aghaie et al, 2012;Kozlowski et al, 2012;Monti et al, 2011), while the TC methods are restricted to simplified problems (Mahadevan et al, 2012;Watson, 2010).…”

Section: Introductionmentioning

confidence: 99%

A tightly coupled scheme for neutronics and thermal–hydraulics using open-source software

Rizwan-uddin

2016

Annals of Nuclear Energy

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Development of a coupled neutronic/thermal-hydraulic tool with multi-scale capabilities and applications to HPLWR core analysis

Cited by 15 publications

References 14 publications

Influence Analysis of Coupled Neutronics and Thermo-Hydraulics on Steady-State Characteristics of Supercritical Water-Cooled Reactor

Influence Analysis of Coupled Neutronics and Thermo-Hydraulics on Steady-State Characteristics of Supercritical Water-Cooled Reactor

Modeling of Technology Evolution (TE) for Nuclear Industry in Aspect of Multidisciplinary R&Ds

A tightly coupled scheme for neutronics and thermal–hydraulics using open-source software

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