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Saturday, July 18, 2020 | History

4 edition of Transient Thermal Hydraulics, Heat Transfer, and Coupled Vessel and Piping Responses found in the catalog.

Transient Thermal Hydraulics, Heat Transfer, and Coupled Vessel and Piping Responses

Y. S. Shin

Transient Thermal Hydraulics, Heat Transfer, and Coupled Vessel and Piping Responses

Presented at the 1995 Joint Asme/Jsme Pressure Vessels and Pipin (Pvp)

by Y. S. Shin

  • 335 Want to read
  • 26 Currently reading

Published by American Society of Mechanical Engineers .
Written in English

    Subjects:
  • Engineering thermodynamics,
  • Industrial chemistry,
  • Material Science,
  • Technology & Industrial Arts

  • The Physical Object
    FormatHardcover
    Number of Pages120
    ID Numbers
    Open LibraryOL7804448M
    ISBN 100791813428
    ISBN 109780791813423

    An analytical solution was derived for the transient response of an insulated aerospace vehicle structure subjected to a simpli ed heat pulse. This simpli ed problem approximates the thermal response of a thermal protection system of an atmospheric entry vehicle. The exact analytical solution is solely a function of two non-dimensional parameters. Numerical Study of Deteriorated Convection Heat Transfer of Supercritical Fluid Flowing Through Vertical Mini Tube at Relatively Low Reynolds Numbers Investigation of Supercritical CO 2 Thermal Hydraulic Characteristics in a Printed Circuit Heat Exchanger. Wen Pressurized Thermal Shock (PTS) Transient Scenarios Screening Analysis With.

    @article{osti_, title = {Combined radiation-convection heat transfer in a pipe}, author = {Chiou, J S}, abstractNote = {The effect of radiation on steam under the reflood steam cooling condition, as during the reflood period in a loss of coolant accident (LOCA), was calculated. A one-dimensional radiative heat flux model was included in the energy transport equation and . Topics: Dimensions, Heat, Heat transfer, Numerical analysis, Simulation, Steady state, Temperature, Thermal hydraulics, Very high temperature reactors Experimental ECCS Sump Strainer Head Loss Testing and the Incorporation of CFD Computed Source Terms for Pressurized Water Reactors.

    Computer control of the immersion heater, in-vessel pumps, and the MCTF allows transient simulations. The two IHXs are designed to contain heat sinks, and the cold wall of the containment vessel simulates cooling by the RVACS. This model is the most complete thermal-hydraulic water model built to date for a U.S. DOE LMR program. Experimental research into pressurized water reactor (PWR) loss-of-coolant phenomena conducted in the Loss-of-Fluid Test (LOFT) facility has given results indicating that for very large pipe breaks the core thermal response is tightly coupled to the fluid hydraulic phenomena during the blowdown phase of the loss-of-coolant transient.


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Transient Thermal Hydraulics, Heat Transfer, and Coupled Vessel and Piping Responses by Y. S. Shin Download PDF EPUB FB2

Get this from a library. Transient thermal hydraulics, heat transfer, and coupled vessel and piping responses: presented at the Joint ASME/JSME Pressure Vessels and Piping Conference, Honolulu, Hawaii, July[Yong W Shin; H Madarame; American Society of Mechanical Engineers. Pressure Vessels and Piping Division.;].

Get this from a library. Transient thermal-hydraulics and coupled vessel and piping system responses, presented at the Pressure Vessels and Piping Conference, San Diego, California, June[Yong W Shin; F J Moody; C Y Wang; American Society of Mechanical Engineers.

Pressure Vessels and Piping Division.;]. There are some coupled codes that use coupled neutronic and thermal–hydraulic effects like CORD-2 (Trkov et al., ), DYNCO (Boroushaki et al., ) and PARCS (Downar et al., ) each of them is proposed for special calculations.

They use simple T–H methods in their calculations and their T–H routines are limited to special by: NUREG/NP LAMS,“SOLA-PTS: A Transient, Three-Dimensional Algorithm for Fluid Thermal Mixing and Wall Heat Transfer in Complex Geometries.” EPRI/NP,“Fluid and thermal Mixing in a Model of cold leg and downcomer with loop flow,” ProjectCreare by: 6.

And MUGTHES can deal with three-dimensional transient thermal-hydraulic problem coupled with three-dimensional transient heat conduction in the surrounding structure in consideration of conjugated heat transfer. In this paper, numerical schemes for thermal-hydraulic simulation employed in MUGTHES are described including LES model.

Jo, Jong Chull, and Moody, Frederick J. "Transient Thermal-Hydraulic Responses of the Nuclear Steam Generator Secondary Side to a Main Steam Line Break." Proceedings of the ASME Pressure Vessels and Piping Conference.

Volume 4: Fluid-Structure Interaction. Anaheim, California, USA. July 20–24, VT04A ASME. Transient Hydraulic Response of a Pressurized Water Reactor Steam Generator to a Feedwater Line Break Using the Nonflashing Liquid Flow Model Contributed by the Pressure Vessel and Piping Division of ASME for publication in the J OURNAL OF P RESSURE V ESSEL Transient Thermal-Hydraulic Responses of the Nuclear Steam Generator.

One-dimensional thermal-hydraulic model was applied to model the coolant circuit. Quasi two-dimensional analysis models for heat transfer of fuel element, ECA and the heat pipe fin were established. Considering the thermoelectric conversion phenomena, an equivalent electric efficiency model was inserted in the ECA model.

Toward this, a pool thermal hydraulics study coupling heat transfer interaction among (i) debris settling on core catcher and hot pool, (ii) core support structure plenum, cold pool and hot pool through inner vessel, and (iii) hot pool and decay heat.

A transient thermal analysis was first examined with coupled and uncoupled heat equations. Temperature distribution results showed that the coupling effect between two pulses can be neglected.

Stress waves due to direct pulsing have been calculated on the target container, investigating the effects of loading rate and structure thickness.

hydraulics, and primary-to-secondary heat transfer. Among these, the single- and two-phase natural circulation and system depressurization, by association to loop thermal-hydraulics.

Thermal hydraulic calculation of the SMART is aimed at confirming its safety and providing the heat transport capability which can match the generated heat by the core. The calculations are performed using a system analysis code, TASS/SMR (Yoon et al., ), developed by the Korea Atomic Energy Research Institute.

Jo, Jong Chull, Min, Bok Ki, and Jeong, Jae Jun. "Validation of a CFD Analysis Model for the Thermal-Hydraulic Response of PWR Steam Generator to a Steam Line Break." Proceedings of the ASME Pressure Vessels and Piping Conference.

Volume 4: Fluid-Structure Interaction. Vancouver, British Columbia, Canada. July 17–21, VT04A ASME. Analysis of a Station Black-Out transient in SMR by using the TRACE and RELAP5 code To cite this article: F De Rosa et al J.

Phys.: Conf. Ser. View the article online for updates and enhancements. Related content RELAPD thermal hydraulic analysis of the target cooling system in the SPES experimental facility. The behavior of lumped systems, shown in Fig.

2 can be interpreted as a thermal time constant b VC R C hA t t p t t 1 1 where Rt is the resistance to convection heat transfer and Ct is the lumped thermal capacitance of the solid. Any increase in Rt or Ct will cause a. Based on the reflood flow and heat transfer characteristics, a thermo-hydraulic analysis model for the reflood phase was developed and presented in this paper.

hydraulics and coupled vessel. Based on the design, a thermal-hydraulic analysis code for heat pipe cooled reactor is developed to analyze steady and transient performance of the designed nuclear reactor.

CAST3M/ARCTURUS: A coupled heat transfer CFD code for thermal–hydraulic analyzes of gas cooled reactors Article (PDF Available) in Nuclear Engineering and Design (15) September.

Get this from a library. Transient thermal hydraulics and resulting loads on vessel and piping systems, presented at the Pressure Vessels and Piping Conference, Nashville, Tennessee, June[F J Moody; Yong W Shin; J D Colton; American Society of Mechanical Engineers.

Pressure Vessels and Piping Division.;]. Results of heat transfer coefficient measurements in an agitated vessel heated or cooled by the liquid media flowing in a helical pipe coil are presented in this paper.

Heat is defined in physics as the transfer of thermal energy across a well-defined boundary around a thermodynamic thermodynamic free energy is the amount of work that a thermodynamic system can perform. Enthalpy is a thermodynamic potential, designated by the letter "H", that is the sum of the internal energy of the system (U) plus the product of pressure .Get this from a library!

Transient thermal-hydraulics in vessel and piping systems: presented at the ASME Pressure Vessels and Piping Conference--JSME co-sponsorship, Honolulu, Hawaii, July[Yong W Shin; F J Moody; Nihon Kikai Gakkai.;].3 Transient Heat Transfer (Convective Cooling or Heating) All the heat transfer problems we have examined have been steady state, but there are often circumstances in which the transient response to heat transfer is critical.

An example is the heating up of gas turbine compressors as they are brought up to speed during take-off.