Results 21 to 30 of about 244,763 (311)
According to advances in high heat flux devices, sufficient thermal management methods shall be developed to dissipate high heat fluxes, especially for small-scale devices.
A. Soleimani, A. Sattari, P. Hanafizadeh
semanticscholar +1 more source
Two-phase flow boiling pressure drop in small channels
AbstractTwo-phase pressure drop, flow instability and boiling regime identifications are an essential step in the design of a variety of plant in the power and process industries. Despite the wide spread applications, significant experimental data on flow boiling in small channel is not available.
Sardeshpande, Madhavi V. +2 more
openaire +1 more source
Numerical Study of the Effect of the Rolling Motion on the Subcooled Flow Boiling in the Subchannel
The marine environment may change the force on the fluid and inevitably influence bubble behavior and the two-phase flow in the reactor core, which are vital to the safety margin of a nuclear reactor.
Yaru Li +5 more
doaj +1 more source
Numerical investigation of the critical heat flux in a 5 × 5 rod bundle with multi-grid
To improve the heat transfer efficiency of the reactor fuel assembly, it is necessary to accurately calculate the two-phase flow boiling characteristics and the critical heat flux (CHF) in the fuel assembly.
Wei Liu +7 more
doaj +1 more source
A crucial parameter remarkably influencing the reliability and accuracy of vapor quality measurements in flow boiling experiments is the measurement of heat loss.
Mehdi Kabir
doaj +1 more source
Evaluation of Correlations of Flow Boiling Heat Transfer of R22 in Horizontal Channels
The calculation of two-phase flow boiling heat transfer of R22 in channels is required in a variety of applications, such as chemical process cooling systems, refrigeration, and air conditioning. A number of correlations for flow boiling heat transfer in
Zhanru Zhou, Xiande Fang, Dingkun Li
doaj +1 more source
Flow boiling and flow condensation are often regarded as two opposite or symmetrical phenomena involving the change of phase. There is a temptation to describe both these phenomena with one only correlation.
Mikielewicz Dariusz +2 more
doaj +1 more source
A subchannel void sensor (SCVS) was developed to measure the cross-sectional distribution of void fraction in a 5×5 heated rod bundle with o.d. 10 mm and heated length 2000 mm, and applied to a boiling two-phase flow experiment under the atmospheric ...
T. Arai +4 more
semanticscholar +1 more source
Flow 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
The present numerical investigation identifies quantitative effects of fundamental controlling parameters on the detachment characteristics of isolated bubbles in cases of pool boiling in the nucleate boiling regime.
Anastasios Georgoulas +2 more
doaj +1 more source

