Mechanistic modeling and correlations for pool-entrainment phenomenon

Kataoka, Isao; Ishii, Masataka

doi:10.2172/6067936

Cited by 27 publications

(48 citation statements)

References 3 publications

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“…Bubbly flow conditions are maintained in the pool as long as j remains below the threshold value for onset of the churn-turbulent flow regime, which is given by [7]:…”

Section: Design Of a Test Facility To Investigate Fundamental Na-co2 mentioning

confidence: 99%

Design of a test facility to investigate fundamental Na-CO2 interations in compact heat exchangers.

Farmer¹,

Kilsdonk²,

Grandy³

2011

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SUMMARYOne of the key objectives of the SFR R&D program is to develop and demonstrate innovative cost reduction and performance enhancing technologies for SFRs. The supercritical carbon dioxide (S-CO 2 ) Brayton cycle power converter system has been identified as one such innovation that could contribute to meeting this objective. One appealing feature of this system is the small footprint that the hardware requires, which is in part due to the use of Printed Circuit Heat Exchangers (PCHEs) as the secondary (Na-to-CO 2 ) heat exchanger as well as the recuperator and cooler modules. Although PCHEs have a high degree of structural integrity, the potential for leak(s) to develop between the sodium and CO 2 coolant channels in the secondary heat exchanger cannot be ruled out, leading to discharge of high pressure CO 2 into the secondary coolant circuit. Due to the robustness of the PCHE design, catastrophic failure leading to gas jet blowdown into the secondary sodium loop is not deemed to be a likely scenario. Rather, small crack(s) (or micro-leaks) may develop in which CO 2 will bleed into the secondary system at a relatively low rate and chemically react with the sodium.The primary focus of the current work is to develop an experiment capability to investigate reaction characteristics under micro-leak conditions. This report summarizes the progress that was made towards meeting this objective this fiscal year. In particular, the facility scaling rationale was developed, and on that basis, the detailed facility design and operating procedures were completed. Based on the design work, fabrication drawings for the three primary system components (i.e., test vessel, dump tank, and separator/vapor trap) were generated and submitted to an outside vendor (i.e., Ability Engineering Technology in South Holland, IL) for fabrication. Fabrication of these components was also completed this year. Plans are to have the facility assembled by the midpoint of FY11 and to begin shakedown testing at that time.

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“…Bubbly flow conditions are maintained in the pool as long as j remains below the threshold value for onset of the churn-turbulent flow regime, which is given by [7]:…”

Section: Design Of a Test Facility To Investigate Fundamental Na-co2 mentioning

confidence: 99%

Design of a test facility to investigate fundamental Na-CO2 interations in compact heat exchangers.

Farmer¹,

Kilsdonk²,

Grandy³

2011

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“…The droplets can be entrained or fall back depending on their inertia and the carrier gas velocity. Data gathered in the bubbly flow regime by Kataoka [9] show the following trends: · The higher the gas superficial velocity in the pool, the higher the droplet mass flux.…”

Section: Open Issues Related To Droplet Formationmentioning

confidence: 99%

The PSI Artist Project: Aerosol Retention and Accident Management Issues Following a Steam Generator Tube Rupture

Gu¨ntay

Dehbi

Suckow

et al. 2002

10th International Conference on Nuclear Engineering, Volume 2

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Steam generator tube rupture (SGTR) incidents, such as those, which occurred in various operating pressurized, water reactors in the past, are serious operational concerns and remain among the most risk-dominant events. Although considerable efforts have been spent to understand tube degradation processes, develop improved modes of operation, and take preventative and corrective measures, SGTR incidents cannot be completely ruled out. Under certain conditions, high releases of radionuclides to the environment are possible during design basis accidents (DBA) and severe accidents. The severe accident codes' models for aerosol retention in the secondary side of a steam generator (SG) have not been assessed against any experimental data, which means that the uncertainties in the source term following an unisolated SGTR concurrent with a severe accident are not currently quantified.The accident management (AM) procedures aim at avoiding or minimizing the release of fission products from the SG. The enhanced retention of activity within the SG defines the effectiveness of the accident management actions for the specific hardware characteristics and accident conditions of concern. A sound database on aerosol retention due to natural processes in the SG is not available, nor is an assessment of the effect of management actions on these processes. Hence, the effectiveness of the AM in SGTR events is not presently known.To help reduce uncertainties relating to SGTR issues, an experimental project, ARTIST (AeRosol Trapping In a Steam generaTor), has been initiated at the Paul Scherrer Institut to address aerosol and droplet retention in the various parts of the SG. The test section is comprised of a scaled-down tube bundle, a full-size separator and a full-size dryer unit. The project will study phenomena at the separate effect and integral levels and address AM issues in seven distinct phases: Aerosol retention in 1) the broken tube under dry secondary side conditions, 2) the near field close to break under dry conditions, 3) the bundle farfield under dry conditions, 4) the separator and dryer under dry conditions, 5) the bundle section under wet conditions, 6) droplet retention in the separator and dryer sections and 7) the overall SG (integral tests). Prototypical test parameters are selected to cover the range of conditions expected in severe accident as well as DBA scenarios.This paper summarizes the relevant issues and introduces the ARTIST facility and the provisional test program which will run between 2003 and 2007.

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“…Only those droplets whose terminal velocities are less than the gas velocity generated by bubble break through will be carried OR Kataoka and Ishii (1984) have developed the following correlation of the data of Golub (1970) and Garner et al (1954) for the eficiency of stable aerosol production above a liquid pool with gas sparging:…”

Section: Aerosol Release Modelmentioning

confidence: 99%

Hanford Waste Tank Bump Accident and Consequence Analysis

Bratzel¹

2000

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Mechanistic modeling and correlations for pool-entrainment phenomenon

Cited by 27 publications

References 3 publications

Design of a test facility to investigate fundamental Na-CO2 interations in compact heat exchangers.

Design of a test facility to investigate fundamental Na-CO2 interations in compact heat exchangers.

The PSI Artist Project: Aerosol Retention and Accident Management Issues Following a Steam Generator Tube Rupture

Hanford Waste Tank Bump Accident and Consequence Analysis

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