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KURENAI : Kyoto University Research Information Repository

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lI . 1 INTRODUCTION<br />

As described in the previous chapter, heat transfer under pxpo-<br />

nential power increase is important in relation to reactivity accident<br />

in a nuclear reactor. Therefore, the transient boiling phenomena have<br />

been studied in detail. However, when the power transient accident occurs<br />

in a pressurized water reacter or in a liquid metal cooled reactor,.. the<br />

heat transfer process in aninitial stage is considered to be of non-boiling<br />

forced convective transient heat transfer. Therefore, in analysing the<br />

problems associated with a reactivity accident, the knowledge of<br />

transient non-boiling heat transferis also indespensable. In the previous<br />

chapter, some experimental results on non-boiling transient heat transfer<br />

coefficient have been reported. However, the obtained correlation was<br />

purely experimental one and not based on the detailed analysis of heat<br />

transfer mechanisms. Therefore, in this chapter, an analytical study<br />

has been carried out on the transient non-boiling forced convective heat<br />

transfer under exponentially increasing heat flux.<br />

There have been some analytical and experimental works on transient<br />

non-boiling heat transfer [1]. Concerning the transient heat transfer analysis<br />

in flows in round tube, annulus and parallel plate, analytical and numerical ana-<br />

lyses have been carried out by Siegel [2-5] , Sparrow and Siegel [6] , Perlmutter and<br />

Siegel [7] , Siegel and Perlmutter [8] , Namatame [9] and Kawamura et al.<br />

[10-12]. Kawamura et al. [10-12] also conducted experiments in annu-<br />

lus. On the other hand, several works have been carried out for flat<br />

plate by Cess [13] , Goodman [14] , Adams et al. [15] , Soliman et al. [16-18] ,<br />

Chao et al. [19,20] , Ishiguro et al'. [21,22] and Hanawa [23-26] . In most<br />

113

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