Modeling of condensation in horizontal tubes

Schaffrath, A.; Krüssenberg, A.-K.; Fjodorow, A; Gocht, Ulrike; Lischke, W.

doi:10.1016/s0029-5493(00)00329-0

Cited by 17 publications

(8 citation statements)

References 12 publications

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“…In order to simulate this process, two different routines were developed (HOTKON and KONWAR) and performed on the ATHLET code, which is also widely used for accident analyses in nuclear power plants. The comparison between experimental data and calculated results using these new routines presented better agreement (Schaffrath et al, 2001). Figure 2 shows the experimental facility and test section which were designed to simulate a horizontal condenser tube (single heat exchanger) of an ESBWR (Wu, 2005).…”

Section: Bibliographical Reviewmentioning

confidence: 75%

Studies on steam condensation with non-condensable gases in a horizontal condenser tube for advanced nuclear reactors using RELAP5

Macedo

Torres

2011

IJNEST

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Horizontal heat exchangers are used in advanced light water nuclear reactors in their passive cooling systems, such as Residual Heat Removal System (RHRS) and Passive Containment Cooling System (PCCS). Horizontal condensation studies of steam with non-condensable gases mixtures in these heat exchangers are very important. This work presents a comparison between simulation results and experimental data in steady state conditions for some inlet pressure, steam and non-condensable gases (air) inlet mass fractions. The test section was modelled and the simulations were performed with the RELAP5 code. Experimental tests were carried out for 200-400 kPa inlet pressure and 5%, 10%, 15% and 20% of inlet air mass fractions. Comparisons between experimental data and simulation results are presented for 200 kPa and 400 kPa pressure conditions and showed good agreement. New correlations for heat transfer coefficients in these steam-air conditions must be theoretically and experimentally studied and implemented in the RELAP5 code.

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Section: Bibliographical Reviewmentioning

confidence: 75%

Studies on steam condensation with non-condensable gases in a horizontal condenser tube for advanced nuclear reactors using RELAP5

Macedo

Torres

2011

IJNEST

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“…Although KONWAR was successfully validated against the NOKO experiments, it has to be considered that the utilized flow pattern map of Tandon et al is originally based on data obtained by experiments with the refrigerants R-12 and R-133 in tubes with internal diameters ranging from 4.8 mm to 15.9 mm. Later on, Schaffrath et al [63] validated the KONWAR model with data from the HORUS test facility [64] and results showed good agreement.…”

Section: Application and Assessment Of 1d Codes For Passive Safety Symentioning

confidence: 99%

Modelling of Passive Heat Removal Systems: A Review with Reference to the Framatome KERENA BWR Reactor: Part I

et al. 2019

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Passive safety systems are an important feature of currently designed and constructed nuclear power plants. They operate independent of external power supply and manual interventions and are solely driven by thermal gradients and gravitational force. This brings up new needs for performance and reliably assessment. This paper provides a review on fundamental approaches to model and analyze the performance of passive heat removal systems exemplified for the passive heat removal chain of the KERENA boiling water reactor concept developed by Framatome. We discuss modelling concepts for one-dimensional system codes such as ATHLET, RELAP and TRACE and furthermore for computational fluid dynamics codes. Part I deals with numerical and experimental methods for modelling of condensation inside the emergency condensers and on the containment cooling condenser while part II deals with boiling and two-phase flow instabilities.

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“…Schaffrath's model [17] was developed for the investigation of the operation mode of the SWR1000 emergency condenser (NOKO test facility). It is based on Tandon's flow regime map [18] for the determination of the actual flow regime and switches to flow regime semi-empirical correlations for the HTC calculation: Soliman for spray flow [19], Nusselt for laminar annular flow, Kosky and Staub for turbulent annular flow [20], Rufer and Kezios for stratified flow [21], Breber et al for slug-plug flow [22].…”

Section: Modelling Of Condensation In a Horizontal Tubementioning

confidence: 99%

“…A single tube test, besides, was provided to clarify the condensation flow regimes inside a horizontal tube and to validate Tandon's flow map condensation model (reported in Figure 9). This experimental campaign led finally to the improvement of ATHLET thermal-hydraulic code [17], implementing the correlations discussed at the end of Section 3.1.…”

Section: Short Review On Experimental Facilitiesmentioning

confidence: 99%

Modelling of Heat Transfer Phenomena for Vertical and Horizontal Configurations of In-Pool Condensers and Comparison with Experimental Findings

Papini

Cammi

2010

Science and Technology of Nuclear Installations

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Decay Heat Removal (DHR) is a fundamental safety function which is often accomplished in the advanced LWRs relying on natural phenomena. A typical passive DHR system is the two-phase flow, natural circulation, closed loop system, where heat is removed by means of a steam generator or heat exchanger, a condenser, and a pool. Different condenser tube arrangements have been developed for applications to the next generation NPPs. The two most used configurations, namely, horizontal and vertical tube condensers, are thoroughly investigated in this paper. Several thermal-hydraulic features were explored, being the analysis mainly devoted to the description of the best-estimate correlations and models for heat transfer coefficient prediction. In spite of a more critical behaviour concerning thermal expansion issues, vertical tube condensers offer remarkably better thermal-hydraulic performances. An experimental validation of the vertical tube correlations is provided by PERSEO facility (SIET labs, Piacenza), showing a fairly good agreement.

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Modeling of condensation in horizontal tubes

Cited by 17 publications

References 12 publications

Studies on steam condensation with non-condensable gases in a horizontal condenser tube for advanced nuclear reactors using RELAP5

Studies on steam condensation with non-condensable gases in a horizontal condenser tube for advanced nuclear reactors using RELAP5

Modelling of Passive Heat Removal Systems: A Review with Reference to the Framatome KERENA BWR Reactor: Part I

Modelling of Heat Transfer Phenomena for Vertical and Horizontal Configurations of In-Pool Condensers and Comparison with Experimental Findings

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