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1.
If a flow obstacle, such as a spacer is placed in a boiling two-phase flow within a channel, the temperature on the surface of the heating tube is severely affected by the existence of the spacer. Under certain conditions, a spacer has a cooling effect, and under other conditions, the spacer causes dryout of the cooling water film on the heating surface. The burnout mechanism, which always occurs upstream of a spacer, however, remains unclear.In a previous paper [Fukano, T., Mori, S., Akamatsu, S., Baba, A., 2002. Relation between temperature fluctuation of a heating surface and generation of drypatch caused by a cylindrical spacer in a vertical boiling two-phase upward flow in a narrow annular channel. Nucl. Eng. Des. 217, 81–90], we reported that the disturbance wave has a significant effect on dryout and burnout occurrence and that a spacer greatly affects the behavior of the liquid film downstream of the spacer.In the present study, we examined in detail the influences of a spacer on the heat transfer and film thickness characteristics downstream of the spacer by considering the result in steam–water and air–water systems. The main results are summarized as follows:
(1) The spacer averages the liquid film in the disturbance wave flow. As a result, dryout tends not to occur downstream of the spacer. This means that large temperature increases do not occur there. However, traces of disturbance waves remain, even if the disturbance waves are averaged by the spacer.
(2) There is a high probability that the location at which burnout occurs is upstream of the downstream spacer, irrespective of the spacer spacing.
(3) The newly proposed burnout occurrence model can explain the phenomena that burnout does occur upstream of the downstream spacer, even if the liquid film thickness tF m is approximately the same before and behind the spacer.

Article Outline

1. Introduction
2. Experimental apparatus and procedure
2.1. Experimental apparatus
2.2. Definition of burnout occurrence on the heating tube
2.3. Experimental conditions
2.4. Current burnout occurrence model in a BWR
3. Experimental results and discussion
3.1. Influence of the spacer on heat transfer characteristics
3.2. Influence of the spacer on film thickness characteristics
3.3. Proposed burnout occurrence model
4. Conclusion
References

1. Introduction

Nuclear power stations must be designed to be highly efficient as well as to operate safely. Based on an experimental result obtained by using a large-scale apparatus, the thermal design of a boiling water reactor is restricted by heat removal from nuclear rods in close vicinity to cylindrical spacers that support the nuclear rods (Arai et al., 1992). However, since this mechanism is not yet fully understood, clarification of the burnout mechanism near the cylindrical spacers in the boiling water reactor is necessary. Several studies, including Yokobori et al. (1989), Sekoguchi et al. (1978) and Feldhaus et al. (2002), have been performed in order to clarify the burnout occurrence mechanism. Although, generally the flow pattern is essentially in two-phase flow, most of the above-mentioned studies did not observe the flow pattern. Few studies have attempted to clarify in detail the burnout or dryout occurrence mechanisms near the spacer by observing the boiling two-phase flow behavior.Based on the information described above, Fukano et al. (1996) made a detailed observation of the behavior of boiling two-phase flow near a flow obstruction in order to clarify the mechanism of dry patch occurrence by placing a cylindrical flow obstruction in a vertical annular channel. The flow obstruction was designed to simulate a cylindrical spacer in an actual boiling water reactor. Furthermore, Fukano et al. (1997) performed an experimental investigation on the effects of the geometry of the spacer, i.e., a grid spacer or a cylindrical spacer, on dry patch occurrence. They clarified that dry patches occur more frequently when the grid spacer is used because the wedge-like gaps formed within the grid spacer hold water near the narrowest region inside the spacer gap through surface tension. Accordingly, typical drainage occurs just beneath the spacer, when the heat flux is not so large (Fukano et al., 1980).Furthermore, the axial distance between the spacers has a strong effect on the critical heat flux near the spacer. In an actual nuclear reactor, for example, the distance of 500 mm was adopted. Fukano (1998) tried to clarify the effect of the existence of an upstream spacer on the dry patch occurrence on the heating surface around a downstream spacer by observing the flow configuration near both spacers in detail. Moreover, Fukano et al. (2003) performed a detailed investigation of the wall temperature fluctuation characteristics near the cylindrical spacer for the case in which repeated dryout and rewetting of the heating surface occurred. As a result, it was clarified that the mechanism of dry patch occurrence was due to the evaporation of a water film that originated primarily from the drainage of water film in the case of low heat flux, and was due to the evaporation of the water film (the base film) in the disturbance wave flow in the case of high heat flux. Fukano et al. (2002) also clarified the influence of the spacer in transient two-phase flow, i.e., the influence on the transition of the operating point on parameters, such as the heat flux, the mass flow rate and the inlet quality of the test section. As a result, even if the flow pattern changes rapidly by the stepwise change of an operation parameter, the flow transition proceeds safely, provided that the change causes an increase in the vapor velocity, i.e., an increase in the shear force acting on the water film. On the other hand, if the change causes a decrease in the vapor velocity, transient burnout may occur, even when the operation condition after the change is less than the steady burnout condition. Furthermore, Mori and Fukano (2003) performed a detailed observation of flow phenomena near a spacer using a high-speed video camera for the case in which burnout occurred in a steady boiling two-phase flow. As a result, it is clarified that the disturbance waves have a strong effect on burnout occurrence, that is, the interval of the disturbance waves is very important because the dry patch always occurs at the base film between the neighboring disturbance waves. In addition, Mori and Fukano (2006) clarified statistically the relationship among the interval of the disturbance waves, dryout of the thin water film and burnout of the heating tube for the case in which a spacer is placed in an annular channel.The main purpose of the present paper is to clarify in detail the influence of a spacer on the heat transfer and film thickness characteristics downstream of a spacer. We will propose later herein a new burnout occurrence model in consideration of the unsteady nature of two-phase flow.

2. Experimental apparatus and procedure

2.1. Experimental apparatus

Fig. 1 shows a schematic diagram of the experimental apparatus of the steam–water system. Test section (1) was placed vertically in a closed forced convection loop. A working fluid, distilled water, was supplied by a feed pump (7) into the test section after passing through a pre-heater (10), where the temperature of the working fluid at the inlet of the test section, i.e., the degree of inlet subcooling was controlled. The two-phase mixture was separated into water and steam in a separator (2) downstream from the exit of the test section. Both the water and the steam were collected in a reservoir (6) after being cooled to below saturation temperature in each condenser (5) in order to prevent cavitation in the feed pump (7).  相似文献   

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The determination of gamma heating levels in material-testing reactors (MTRs) is of crucial importance as gamma heating affects both safety and performance parameters of MTRs [1 Amharrak H, Di Salvo J, Lyoussi A, Carette M, Reynard-Carette C. State of the art on nuclear heating in a mixed (n/gamma) field in research reactors. Nucl Instrum Methods A. 2014;749:5767.[Crossref], [Web of Science ®] [Google Scholar],2 Brun J, Reynard-Carette C, Lyoussi A, Merroun O, Carette M, Janulyte A, Zerega Y, Andre J, Bignan G, Chauvin J-P, Fourmentel D, Gonnier C, Guimbal P, Malo J-Y, Villard J-F. Numerical and experimental calibration of calorimetric sample cell dedicated to nuclear heating measurements. IEEE Trans Nucl Sci. 2012;59:31733179.[Crossref], [Web of Science ®] [Google Scholar]]. The required accuracy (5% at one standard deviation) makes it necessary to calibrate bias and uncertainty associated with MTR gamma-heating calculations. Main steps of bias determination for gamma-heating calculations include, first, the development of a calculation methodology with the controlled use of physical approximations; second, the interpretation of gamma-heating measurements with reference calculations so as to determine bias supposed to be mainly due to nuclear data.  相似文献   

5.
In this paper, the effects of Coulomb elctron-ion collisions and plasma density gradient, \(\eta\), on the Weibel instability in inertial confinement fusion are investigated. The results are indicative that the corrected collision of Weibel instability growth rate of the relativistic region near the corona, \(\eta >0.3\), increases with increasing relativistic parameter, \(\upgamma\). Also, near the fuel core as \(\eta\) goes down, the corrected collisional growth rate decreases with increasing \(\upgamma\) for \(\mathrm{{\upgamma }}<6\) and and increases with increasing \(\upgamma\) for \(\upgamma >6\). Therefore, for \(\upgamma <6\), the effect of collision and fuel density gradient tend to stabilize the Weibel instability in fuel core, with the Weibel growth rate below the collisionless value. Also deposition condition of relativistic electron beam energy can be shifted to the fuel core for the suitable ignition.  相似文献   

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