The Pb–Bi cooled XADS status of development

Cinotti, L.; Gherardi, G.

doi:10.1016/s0022-3115(01)00721-8

Cited by 47 publications

(16 citation statements)

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“…Conceptual designs of lead-bismuth (45Pb-55Bi) cooled fast reactors (LFRs) and Pb-Bi target type accelerator driven system (ADS) have been proposed by a number of researchers [1][2][3][4][5]. The compatibility of cladding, structural and window materials in the Pb-Bi flow at high temperature is one of the critical issues.…”

Section: Introductionmentioning

confidence: 99%

Study on control of oxygen concentration in lead–bismuth flow using lead oxide particles

Kondo

Takahashi

Miura

et al. 2006

Journal of Nuclear Materials

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Section: Introductionmentioning

confidence: 99%

Study on control of oxygen concentration in lead–bismuth flow using lead oxide particles

Kondo

Takahashi

Miura

et al. 2006

Journal of Nuclear Materials

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“…XADS 1) and RBEC-M 2) are given in Table 1. It is seen that, although the chosen tests cover a large range of two-phase flow parame-ters, there is still a need for further experimental studies.…”

Section: Summary Of the Experimental Datamentioning

confidence: 99%

Development of a Drift-flux Model for Heavy Liquid Metal/Gas Flow

Mikityuk

Coddington

Chawla

2005

Journal of Nuclear Science and Technology

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The gas lift pump concept based on the bubbling of an inert gas into the primary reactor coolant to enhance natural circulation is currently considered in a number of PbBi-cooled reactor concepts. Thus, the analysis of available void fraction data and the development of two-phase heavy liquid metal/gas flow calculational models have become an important issue in the study of advanced nuclear reactor systems. In the absence of the detailed two-phase flow information needed to develop a flow regime map and the associated interfacial relations, drift-flux models have often been used in the thermal-hydraulic analysis of nuclear and other systems. Accordingly, we consider, in the current paper, the analysis of five sets of experimental data with different geometries, working fluids, flow rates and void fraction ranges, with a view to obtaining a best fit to the data in the form of a drift-flux model. The results of the analysis show that, for systems with flowing fluid, it is possible to represent the heavy liquid metal void fraction data in the form of a drift-flux correlation with a residual error of as low as 0.016, thus offering an improvement over existing void correlations.

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“…The configuration of the primary system is pool-type [2,3], similar to that of most sodium-cooled reactors, which has important beneficial features. These include the Reactor Vessel ( Fig.…”

Section: Design a The Lbe-cooled Xadsmentioning

confidence: 99%