Results 71 to 80 of about 8,843 (212)
International Journal of Energy Research, Volume 2025, Issue 1, 2025.This study examines the heat transfer and pressure drop characteristics of water/aluminum oxide (Al2O3) nanofluid flow in a semi‐twisted tube within solar collector systems. The investigation focuses on the influence of varying nanofluid concentrations and twisted tube lengths on thermal performance and friction factor.
Hamed Najafpoursani +4 more
wiley +1 more source
Case Studies in Thermal EngineeringFlow boiling in the rod bundle channel is an important phenomenon in nuclear reactors. The local inhomogeneous void fraction distribution in the flow channel will affect the flow and heat transfer in two phase flow.
Sui-Jun Gong +5 more
doaj +1 more source
Multifactoring concept – A key to investigation of forced-eoiling in microsystems [PDF]
, 2009 This paper was presented at the 2nd Micro and Nano Flows Conference (MNF2009), which was held at Brunel University, West London, UK. The conference was organised by Brunel University and supported by the Institution of Mechanical Engineers, IPEM, the ...
2nd Micro and Nano Flows Conference (MNF2009) +1 more
core
Phase appearance or disappearance in two-phase flows [PDF]
, 2011 This paper is devoted to the treatment of specific numerical problems which appear when phase appearance or disappearance occurs in models of two-phase flows. Such models have crucial importance in many industrial areas such as nuclear power plant safety
A Guelfi +32 more
core +2 more sources
RELAP5/MOD3 subcooled boiling model assessment [PDF]
, 1998 This report presents the assessment of the RELAP5/Mod3 (5m5 version) code subcooled boiling process model which is based on a variety of experiments. The accuracy of the model is confirmed for a wide range of regime parameters for the case of uniform heating along the channel.
Devkin, A. S., Podosenov, A. S.
openaire +2 more sources
International Journal of Energy Research, Volume 2025, Issue 1, 2025.The present study assessed the drift‐flux parameter correlations implemented in the TRACE code, the flagship thermal‐hydraulic analysis code developed by the United States Nuclear Regulatory Commission (US NRC). The code is architected on the basis of a two‐fluid model.
Takashi Hibiki +2 more
wiley +1 more source
Booster propulsion/vehicle impact study, 2 [PDF]
This is the final report in a study examining the impact of launch vehicles for various boost propulsion design options. These options included: differing boost phase engines using different combinations of fuels and coolants to include RP-1, methane ...
Carson, C. +3 more
core +1 more source
Numerical Study on Subcooled Pool Boiling
ASME/JSME 2011 8th Thermal Engineering Joint Conference, 2011 This study focuses on the clarification of the heat transfer characteristics of the subcooled pool boiling, the discussion on its mechanism, and finally the establishment of a boiling and condensation model for numerical simulation on the subcooled pool boiling phenomena.
Yasuo OSE, Tomoaki KUNUGI
openaire +1 more source
Forced-flow once-through boilers [PDF]
A compilation and review of NASA-sponsored research on boilers for use in spacecraft electrical power generation systems is presented. Emphasis is on the heat-transfer and fluid-flow problems.
Gray, V. H. +2 more
core +1 more source
Assessment of CTF boiling transition and critical heat flux modeling capabilities using the OECD/NRC BFBT and PSBT benchmark databases [PDF]
, 2011 The need to refine models for best-estimate calculations, based on good-quality experimental data, has been expressed in many recent meetings in the field of nuclear applications.
Avramova, Maria, Cuervo Gómez, Diana
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