Application of the finite volume method to the radial conduction model of the CATHENA code

Kim, Hyoung Tae; Rhee, Bo Wook; Park, Joo Hwan

doi:10.1016/j.anucene.2006.04.011

Cited by 8 publications

(5 citation statements)

References 4 publications

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“…3, it can be seen clearly that the results predicted by the FEM are in good agreement with the exact solution of Ref. [24], which indicates the present FEM model could accurately predict the radial heat transfer problem.…”

Section: Heat Transfer Model Of Coke Chambersupporting

confidence: 76%

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Rapid reconstruction of temperature field of coke chamber based on POD-BP and Tikhonov method

et al. 2023

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As the key equipment of delayed coking unit, the coking chamber generally uses the cycle heating and cooling process to produce products. Due to the large temperature rise and fall process of the cycle, the coke chamber runs under harsh thermal conditions for a long time, and the thermal stress generated by temperature fluctuation is one of the main reasons for the failure of the coke chamber structure. However, the working state of coking chamber is complex, and the traditional numerical method cannot realize timely monitoring, so it is of great practical significance to study the new method to realize timely monitoring. In this paper, POD-BP reduced order models under the second and third thermal boundary conditions are established by studying the coke chamber in the production process. The models are applied to the inversion of the spatial heat flux distribution and the calculation of the temperature field of the coke chamber, which greatly improves the calculation speed of the inversion. It has been proved that the proposed method has the advantages of good real-time performance, high precision, strong anti-interference ability and strong operability, which provides a detection method for the real-time reconstruction of temperature field and production state of coke chamber.

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Section: Heat Transfer Model Of Coke Chambersupporting

confidence: 76%

“…The heat transfer model, thermophysical parameter settings and boundary conditions are the same as those in Ref. [24]. As shown in Fig.…”

Section: Heat Transfer Model Of Coke Chambermentioning

confidence: 99%

Rapid reconstruction of temperature field of coke chamber based on POD-BP and Tikhonov method

et al. 2023

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“…By a one-dimensional analysis, [7] determined the temperature distribution of a homogenous cylinder through CATHENA software with FVM (Finite Volume Method) and FEM (Finite Elements Method). FVM delivers better results even with a less refined mesh, while FEM even produced an inconsistent result (increase in temperature when the system was submitted to cooling effects).…”

Section: Introductionmentioning

confidence: 99%

Two-dimensional transient thermal analysis of a fuel rod by finite volume method

Costa¹,

Silva²,

Lira³

2021

Braz. J. Rad. Sci.

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One of the greatest concerns when studying a nuclear reactor is the warranty of safe temperature limits all over the system at all times. The preservation of core structure along with the constraint of radioactive material into a controlled system are the main focus during the operation of a reactor. The purpose of this paper is to present the temperature distribution for a nominal channel of the AP1000 reactor developed by Westinghouse Co. during steady-state and transient operations. In the analysis, the system was subjected to normal operation conditions and then to blockages of the coolant flow. The time necessary to achieve a new safe stationary stage (when it was possible) was presented. The methodology applied in this analysis was based on a two-dimensional survey accomplished by the application of Finite Volume Method (FVM). A steady solution is obtained and compared with an analytical approach that disregards axial heat transport to determine its relevance. The results show the importance of considering axial heat transport in this type of study. A transient analysis shows the behavior of the system when submitted to coolant blockage at channel’s entrance. Three blockages were simulated (10%, 20% and 30%) and the results show that, for a nominal channel, the system can still be considerate safe (there’s no bubble formation until that point).

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“…Yapici et al [2] investigated the maximum temperatures in centerline of the fuel rod for different clad outer surface temperatures, melting points of the fuel materials, temporal heat generation, temperature distribution in the nuclear fuel rod and temporal variation of the neutronic data during rejuvenation periods. In [3] Kim et al developed the one-dimensional heat conduction model to determine the temperatures distribution from the fuel center to cladding surface in the radial direction.…”

Section: Introductionmentioning

confidence: 99%

“…This dependence has been intensively studied for prolonged lifetime of existing reactors. There are many papers in which the authors studied the different aspects of this problem [2][3][4][5][6][7]. Yapici et al [2] investigated the maximum temperatures in centerline of the fuel rod for different clad outer surface temperatures, melting points of the fuel materials, temporal heat generation, temperature distribution in the nuclear fuel rod and temporal variation of the neutronic data during rejuvenation periods.…”

Section: Introductionmentioning

confidence: 99%

Thermal regimes of high burn-up nuclear fuel rod

Kudryashov¹,

Khlunov²,

Chmykhov³

2010

Communications in Nonlinear Science and Numerical Simulation

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The temperature distribution in the nuclear fuel rods for high burn-up is studied. We use the numerical and analytical approaches. It is shown that the time taken to have the stationary thermal regime of nuclear fuel rod is less than one minute. We can make the inference that the behavior of the nuclear fuel rod can be considered as a stationary task. Exact solutions of the temperature distribution in the fuel rods in the stationary case are found. Thermal regimes of high burn-up the nuclear fuel rods are analyzed.Comment: 24 pages, 9 figure

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Application of the finite volume method to the radial conduction model of the CATHENA code

Cited by 8 publications

References 4 publications

Rapid reconstruction of temperature field of coke chamber based on POD-BP and Tikhonov method

Rapid reconstruction of temperature field of coke chamber based on POD-BP and Tikhonov method

Two-dimensional transient thermal analysis of a fuel rod by finite volume method

Thermal regimes of high burn-up nuclear fuel rod

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