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Journal ArticleDOI

Diameter effect on critical heat flux

TLDR
In this paper, a new diameter correction factor was proposed to predict the critical heat flux look-up table (CHF LUT) for various applications, including design and safety analysis of nuclear reactors.
About
This article is published in Nuclear Engineering and Design.The article was published on 2009-02-01. It has received 35 citations till now. The article focuses on the topics: Critical heat flux & Water flow.

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Citations
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Journal ArticleDOI

Experimental investigation on convective heat transfer of supercritical RP-3 in vertical miniature tubes with various diameters

TL;DR: In this paper, convective heat transfer of hydrocarbon fuel RP-3 at supercritical pressures in vertical micro-tubes with inner diameters of 0538mm, 109mm and 182mm under heating conditions were experimented and analyzed with wide range of supercritical status Also, inner diameter effect on heat transfer were compared at identical conditions.
Journal ArticleDOI

Diameter effect on supercritical heat transfer

TL;DR: In this article, a review of the literature on the effect of tube diameter on heat transfer at supercritical (SC) pressures is presented, based on SC heat transfer data obtained in tubes with a diameter range of 3.18 to 38.1mm, cooled by carbon dioxide, water, R-22 and R-12.
Journal ArticleDOI

On the prediction of critical heat flux using a physics-informed machine learning-aided framework

TL;DR: In this article, a physics-informed machine learning (ML)-aided hybrid framework is proposed to achieve superior predictive capabilities for the critical heat flux (CHF) corresponding to the departure from nucleate boiling crisis.
Dissertation

The design of a compact integral medium size PWR : the CIRIS

TL;DR: In this paper, the authors propose a method to solve the problem of nuclear nuclear power plant design using a nuclear power station, and demonstrate its performance in the field of nuclear science and engineering.
Journal ArticleDOI

The design of a compact integral medium size PWR

TL;DR: In this article, the International Reactor Innovative and Secure (IRIS) was designed with 8 Once-Through Helically Coiled Steam Generators (OTHSG) located above the core, in an annular region between the riser and the pressure vessel wall.
References
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Journal ArticleDOI

The 1995 look-up table for critical heat flux in tubes

TL;DR: An updated version of the look-up table for critical heat flux (CHF) has been developed jointly by AECL Research (Canada) and IPPE (Obninsk, Russia) as mentioned in this paper.
Journal ArticleDOI

1986 AECL-UO Critical Heat Flux Lookup Table

TL;DR: In this paper, the critical heat flux (CHF) lookup table is used for predicting CHF for water over a very wide range of conditions and geometries, especially over the ranges where CHF data are scarce.
Journal ArticleDOI

Critical heat flux (CHF) for water flow in tubes—II.: Subcooled CHF correlations

TL;DR: In this article, two non-dimensional, sub-cooled CHF correlations were formulated, containing only five adjustable constants and whose unique functional forms were determined without using a statistical analysis but rather using the parametric trends observed in less than 10% of the subcooled data.
Journal ArticleDOI

Boiling burnout and flow instabilities for water flowing in a round tube under atmospheric pressure

TL;DR: In this paper, an experiment with water flowing in a round tube at atmospheric pressure was performed to study critical heat flux (CHF) at low mass velocities, flow stagnation and flow reversal conditions.
Journal ArticleDOI

Effect of channel geometry on critical heat flux for low pressure water

TL;DR: In this paper, the effect of channel geometry on critical heat flux at low velocity and pressure conditions was investigated and it was shown that the difference in CHF at these mass velocities between a round tube and the other channel geometries was attributed mainly to the existence of an unheated wall which cause a non-uniform distribution of liquid film.
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