Capability of the RELAP5 code to simulate natural circulation behavior in test facilities

Mangal, Amit; Jain, Vikas; Nayak, Arun K.

doi:10.1016/j.pnucene.2012.06.005

Cited by 54 publications

(10 citation statements)

References 6 publications

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“…Using such low-order scheme to make the convection terms of conservation equations discrete produces excessive numerical diffusion. This disadvantage has been realized in many nuclear thermal-hydraulics applications such as hydraulic load analysis of loss of coolant accident [25], long term transient natural circulation flow [26,27], flow instability [28] or stability analysis [29], and boron solute transport [30]. In the past, there are many classical linear schemes like central-difference scheme (CD), QUICK, third-order upwind scheme (TOU), Fromm scheme [31], and second-order upwind scheme (SOU) to reduce high numerical diffusion [32].…”

Section: Introductionmentioning

confidence: 99%

Implementation and Comparison of High-Resolution Spatial Discretization Schemes for Solving Two-Fluid Seven-Equation Two-Pressure Model

Wu¹,

Chao²,

Wu³

et al. 2017

Science and Technology of Nuclear Installations

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As compared to the two-fluid single-pressure model, the two-fluid seven-equation two-pressure model has been proved to be unconditionally well-posed in all situations, thus existing with a wide range of industrial applications. The classical 1st-order upwind scheme is widely used in existing nuclear system analysis codes such as RELAP5, CATHARE, and TRACE. However, the 1st-order upwind scheme possesses issues of serious numerical diffusion and high truncation error, thus giving rise to the challenge of accurately modeling many nuclear thermal-hydraulics problems such as long term transients. In this paper, a semiimplicit algorithm based on the finite volume method with staggered grids is developed to solve such advanced well-posed twopressure model. To overcome the challenge from 1st-order upwind scheme, eight high-resolution total variation diminishing (TVD) schemes are implemented in such algorithm to improve spatial accuracy. Then the semi-implicit algorithm with high-resolution TVD schemes is validated on the water faucet test. The numerical results show that the high-resolution semi-implicit algorithm is robust in solving the two-pressure two-fluid two-phase flow model; Superbee scheme and Koren scheme give two highest levels of accuracy while Minmod scheme is the worst one among the eight TVD schemes.

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Section: Introductionmentioning

confidence: 99%

Implementation and Comparison of High-Resolution Spatial Discretization Schemes for Solving Two-Fluid Seven-Equation Two-Pressure Model

Wu¹,

Chao²,

Wu³

et al. 2017

Science and Technology of Nuclear Installations

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show abstract

“…With this study, it can be concluded that there can be disparity in the predicted results using RELAP5 and the experiments even if the most appropriate nodalization scheme adopted. The disparity in the predicted results and experimental data can be attributed to the constitutive relations used in RELAP5, which are semi-empirical in nature (Mangal et al, 2012).…”

Section: Natural Circulation Flow Instabilities and Heat Transfermentioning

confidence: 95%

“…In a study conducted by Mangal et al (2012), a numerical simulation was performed by using three different nodalization schemes for an experimental facility (Kumar et al, 2000). The three different nodalization schemes were classified as coarse, base, and fine.…”

Section: Natural Circulation Flow Instabilities and Heat Transfermentioning

confidence: 99%

A review: passive system reliability analysis – accomplishments and unresolved issues

2014

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“…RELAP5 is mainly used for the design and safety analysis of nuclear plants, advanced fluid systems and experiments [25,26]. The aim of the RELAP5 code development effort from the beginning was to produce a code that includes important first-order effects necessary for accurate prediction of system transients [27]. RELAP5 allows for the simulation of probable thermal-hydraulic transients in nuclear facilities under a large variety of postulated accident conditions such as loss of coolant, loss of flow, power excursion as well as operational transients and other postulated transients [28].…”

Section: Description Of the Codementioning

confidence: 99%

Modeling and simulation of a natural circulation water-tube steam boiler

et al. 2019

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In the present work, the overall behavior of a steam boiler is investigated using RELAP5/MOD3.2 system code at three different operating loads. Main thermal-hydraulic parameters are analyzed at steady-states corresponding to 60%, 100% and 110% of the boiler nominal load. RELAP5 system code is widely used in the design and safety analysis of nuclear reactor installations as well as for conventional facilities in recent years. The steam boiler studied herein is a water-tube natural circulation type used in a natural gas liquefaction complex for superheated steam production purposes. A complete model of the steam boiler has been developed for the RELAP5 code. This model, that is also suitable for transient simulation, has been used for the reconstruction of three steady-state tests in order to assess the steam boiler safety features during the operation. The model includes all parts that can eventually influence the safety of the steam boiler particularly the control and regulation system. A qualification process has been undertaken in the aim to verify the capability of the model to reproduce the main parameters of the steam boiler. This process revealed that RELAP5 system code results matches significantly the experimental data of the steam boiler. Finally, it should be mentioned that the results obtained so far are very encouraging for studying the general behavior of the steam boiler in transient operating conditions, as well as for evaluating its safety under hypothetical scenarios. This step will be undertaken in the near future and will allow the check of the code capability to simulate thermal-hydraulic phenomena occurring in the steam boiler during transient operation.

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Capability of the RELAP5 code to simulate natural circulation behavior in test facilities

Cited by 54 publications

References 6 publications

Implementation and Comparison of High-Resolution Spatial Discretization Schemes for Solving Two-Fluid Seven-Equation Two-Pressure Model

Implementation and Comparison of High-Resolution Spatial Discretization Schemes for Solving Two-Fluid Seven-Equation Two-Pressure Model

A review: passive system reliability analysis – accomplishments and unresolved issues

Modeling and simulation of a natural circulation water-tube steam boiler

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