1 edition of **Two-phase flow and heat transfer in rod bundles.** found in the catalog.

Two-phase flow and heat transfer in rod bundles.

- 6 Want to read
- 22 Currently reading

Published
**1969** by American Society of Mechanical Engineers in New York .

Written in English

- Nuclear fuel elements -- Congresses.,
- Two-phase flow -- Congresses.,
- Heat -- Transmission -- Congresses.

**Edition Notes**

Statement | Edited by V. E. Schrock. |

Contributions | Schrock, V. E., American Society of Mechanical Engineers. Heat Transfer Division. |

Classifications | |
---|---|

LC Classifications | TK9207 .T9 |

The Physical Object | |

Pagination | vi, 94 p. |

Number of Pages | 94 |

ID Numbers | |

Open Library | OL5428426M |

LC Control Number | 73028391 |

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This book provides comprehensive coverage of post-dryout heat transfer, discussing such essential topics as post-dryout heat transfer in dispersed flow, interpretation and use of transient data in surface rewetting by reinstatement of flow or by reducing heat flux, rod bundles, two-phase flow occurrences in the post-dryout region, various Cited by: Two-phase flow and heat transfer in rod bundles.

Presented at the winter annual meeting of the American Society of Mechanical Engineers, Los Angeles, California, Novem [V E Schrock; American Society of Mechanical Engineers. Annular Two-Phase Flow presents the wide range of industrial applications of annular two-phase flow regimes.

This book discusses the fluid dynamics and heat transfer aspects of the flow pattern. Organized into 12 chapters, Two-phase flow and heat transfer in rod bundles. book book begins with an overview of the classification of the various types of interface distribution observed in Edition: 1.

Two-phase flow heat exchangers are vital components of systems for power generation, chemical processing, and thermal environment control. The art and science of the design of such heat exchangers have advanced considerably in recent years.

This is due to better understanding of the fundamentals of. Completely updated, this graduate text describes the current state of boiling heat transfer and two-phase flow, in terms through which students can attain a consistent understanding.

Prediction of real or potential boiling heat transfer behaviour, both in steady and transient states, is covered to aid engineering design of reliable and effective systems. The current state of knowledge on the prediction of two-phase flow patterns, pressure drop, heat transfer coefficients, and the critical heat flux condition in crossflow boiling on the shellside of multi-tube bundles is described in this chapter.

The mechanisms governing the processes are discussed. Single-phase convective results show that the independence principle can be applied to the case that all tubes were heated in inclined rod bundles.

With respect to two-phase results, the local flow boiling heat transfer coefficient increases from the bottom row to the eleventh row and then can be considered as a constant value from the eleventh row to the top by: 7.

Post-Dryout Heat Transfer Coefficient of High-Pressure Steam-Water Two-Phase Flow in Multi-Rod Bundle. Journal of Nuclear Science and Technology: Vol. 25, No. 1, pp. Cited by: 2. Special steam temperature probes, developed earlier at Lehigh for tests in single tubes, were modified for use in the rod bundle.

Each test provided measurements of system pressure, coolant flow rate, wall heat flux, wall temperatures, two-phase equilibrium qualities, and vapor superheat temperatures.

These primary data permitted determination of wall heat transfer coefficients, nonequilibrium vapor Cited by: Engineering Data Book III. Two-Phase Pressure Drops The frictional pressure drop in two-phase flows is typically predicted using separated flow models.

The first of these analyses was performed by Lockhart and Martinelli () and then followed by many Size: KB. Professors and students will find this "Encyclopedia of Two-Phase Heat Transfer and Flow" particularly exciting, as it contains authored books and thorough state-of-the-art reviews on many basic and special topics, such as numerical modeling of two-phase heat transfer and adiabatic bubbly and slug flows, the unified annular flow boiling model, flow pattern maps, condensation and.

Heat Transfer: Current Applications of Air Conditioning deals with problems and applications of air conditioning. The discussions are organized around non-stationary heat transfer through walls; study of confined rooms or enclosures; calculation of cooling loads; heat transfer with two-phase refrigerants; measurement of thermal conductivity and water vapour permeability of insulating Book Edition: 1.

The Rod Bundle Heat Transfer (RBHT) Facility is a full length simulation of a portion of a Pressurized Water Reactor (PWR) fuel assembly. The bundle is a 7 by 7 rod array with four unheated corner rods and 45 heated electrical rod which simulate a 17 by 17 PWR fuel assembly.

The rod Bundle Heat Transfer Facility is full length, m (12 ft). Two-phase flow on the shell side of a shell and tube heat exchanger is complex. Several studies have produced flow pattern maps that show surprising differences in flow regime boundaries for data sets that contain relatively small variations in fluid and flow by: 4.

Closure to “Discussions of ‘Mass Flux and Enthalpy Distribution in a Rod Bundle for Single- and Two-Phase Flow Conditions’” (, ASME J. Heat Transfer, 93, pp. –) J. Heat Transfer (May, )Cited by: Fluid flow and heat transfer studies were carried out experimentally.

Forced flow of air was caused through 7-rod test sections representing finite arrays. Experimental set-up Three identical sets of 7-rod bundle were made for fluid flow and heat transfer measurements. The rods. About the Author John R Thome is Professor of Heat and Mass Transfer at the Ecole Polytechnique Fédérale de Lausanne (EPFL), Switzerland sincewhere he directs the two-phase flow and heat transfer research laboratory (LTCM) with 20 some post-docs and PhD students, see webpage- Price: $ The convective heat transfer for turbulent flow through rod bundles representative of nuclear fuel rods used in pressurized water reactors is examined.

About the Author John R Thome is Professor of Heat and Mass Transfer at the Ecole Polytechnique Fédérale de Lausanne (EPFL), Switzerland sincewhere he directs the two-phase flow and heat transfer research laboratory (LTCM) with 20 some post-docs and PhD : John R Thome.

Convective boiling (heat transfer models and design methods for evaporation inside tubes and outside tube bundles). Combined heat and mass transfer in phase change processes (condensation in presence of non-condensable gas and evaporation of mixtures. Keywords.

Two-phase heat transfer, two-phase flow, condensation, convection. Professors and students will find this "Encyclopediaa of Two-Phase Heat Transfer and Flow" particularly exciting, as it contains authored books and thorough state-of-the-art reviews on many basic and special topics, such as numerical modeling of two-phase heat tranfser and adiabatic bubbly and slug flows, the unified annular flow boiling model.

Two-phase flow heat exchangers are vital components of systems for power generation, chemical processing, and thermal environment control. The art and science of the design of such heat exchangers have advanced considerably in recent years. Total and Local Heat Transfer and Pressure Drop of Staggered and InLine Other editions - View all.

Heat Exchangers: Thermal-Hydraulic Fundamentals and Design Sadik Kakac Snippet view - -side shown in Fig solution steam step change subcooled surface area temperature difference thermal tube bundle turbulent flow two-phase two-phase.

two-phase flow and heat transfer in multirod geometries: subchannel and pressure drop measurements in a nine-rod bundle for diabatic and adiabatic conditions. Showing of pages in this by: Two-phase flow heat transfer related to safety and operation of conventional and advanced designs of nuclear reactor systems and components can be addressed.

Potential topics include, but are not limited to: Two-phase flow and heat transfer fundamentals; Boiling and condensation heat transfer; CHF and post-CHF heat transfer in light water reactors. Two‐phase flow regimes With reference to upflow in vertical channel, one can (loosely) identify several flow regimes, or patterns, whose occurrence, for a given fluid, pressure and channel geometry, depends on the flow quality and flow rate.

The main flow regimes are reported in Table 1 and shown in Figure 3. Note that what values. Thermal Hydraulics Two-Phase Flow and Heat Transfer Fundamentals ICONE Three-Dimensional Standing Pressure Waves in Bubbly Mixtures p.

1 ICONE Interfacial Area Transport in Bubbly Flow Systems p. 15 ICONE An Extended Two-Fluid Model for Interface Behavior in Gas-Liquid Two-Phase Flow p. Title: Heat transfer near spacer grids in rod bundles Heat transfer data from several sources have been assembled which show the effect of spacer grids on local heat transfer within a rod bundle.

Both single phase (air and steam) data and two phase (steam/water) data show heat. “A General Correlation for Saturated Two-Phase Flow Boiling Heat Transfer Inside Horizontal and Vertical Tubes,” J.

Heat Transfer, (1)–, Google Scholar Katto, Y. and Haramura, Y., “Critical Heat Flux on a uniformly heated horizontal cylinder in an upward cross flow of saturated liquid,” Int. Journal Heat Mass Transfer. Void fraction and friction pressure drop measurements were made for an adiabatic, vertical two‐phase flow of air‐water across two horizontal, in‐line, 5 × 20 rod bundles, one with a pitch‐to‐diameter ratio, P/D, ofthe other For both bundles the average void fraction showed a strong mass velocity effect and values were significantly less than those predicted by a.

assemblies. The spacer grids have been found to have significant effects on flow in a rod bundle during a LOCA. The present work focuses on single-phase steam cooling and the effects that spacer grids have on the thermal hydraulics of single-phase flow and heat transfer.

It is important to understand and accurately model single-phase flow and heatCited by: 2. effects of system parameters on the two-phase flow and heat transfer behavior in a rod bundle Conference Paper (PDF Available) January with 37 Reads How we measure 'reads'. This book provides comprehensive coverage of post-dryout heat transfer, discussing such essential topics as post-dryout heat transfer in dispersed flow, interpretation and use of transient data in surface rewetting by reinstatement of flow or by reducing heat flux, rod bundles, two-phase flow occurrences in the post-dryout region, various.

Effects of system parameters on the two-phase flow and heat transfer behavior in a rod bundle Garrett, G. R., Beck, F. R., Jin, Y., Cheung, F. B., Bajorek, S. The spacer grids have been found to have significant effects on flow in a rod bundle during a LOCA. The present work focuses on single-phase steam cooling and the effects that spacer grids have on the thermal hydraulics of single-phase flow and heat by: 2.

SINGLE-PHASE HEAT TRANSFER IN MICRO-CHANNELS Single Channel Flow Heat Transfer in Multiple Micro-channels MANIFOLD SELECTION AND DESIGN Single-Phase Flow Two-Phase Flow NUMERICAL SIMULATION OF FLOW IN MANIFOLDS TWO-PHASE HEAT TRANSFER IN MICRO-CHANNELS CONCLUSIONS REFERENCES.

NOC on Two phase flow and heat transfer - Duration: 4 minutes, 7 seconds. views; 3 years ago; Two phase flow and heat transfer I Course About Video - Duration: 4 minutes, 7 seconds. An, B. Kim *, "Numerical investigation of film boiling heat transfer on the horizontal surface in an oscillating system with low frequencies," Nuclear.

In fluid mechanics, two-phase flow is a flow of gas and liquid — a particular example of multiphase -phase flow can occur in various forms, such as flows transitioning from pure liquid to vapor as a result of external heating, separated flows, and dispersed two-phase flows where one phase is present in the form of particles, droplets, or bubbles in a continuous carrier phase (i.e.

It is known that introduction of the gas phase into the liquid flow leads to flow restructuring and can significantly change the key thermal-hydraulic flow parameters, for example, the heat transfer coefficient. This paper presents the results of an experimental study of an ascending bubble flow in a vertical assembly of 3×3 rods.

Distilled water was used as a working liquid. Since the same mathematics describes two-phase and two-component flows, the two expressions can be treated as synonymous. Multiphase flow versus heat transfer.

The analysis of multiphase systems can include consideration of multiphase flow and multiphase heat transfer. When all of the phases in a multiphase system exist at the same temperature.of the array and the two-phase flow and heat transfer involved in nuclear reactors.

The geometric complexity stems from the high degree of freedom associated with parallel rod arrays. Rod diameter, rod-to-rod pitch, rod spaces type and location, and, for arrays within shrouds, the spacing between rods and shroud as well as the.Butterworth D and Hewitt GF Eds Two Phase Flow and Heat Transfer Oxford from PHYSIC at National Research Nuclear University MEPhI Butterworth d and hewitt gf eds two phase flow and Gellerstedt, J.S., et al., “Correlation of critical heat flux in a bundle cooled by pressurized water,” Two-Phase Flow and Heat Transfer in Rod.