共查询到20条相似文献,搜索用时 15 毫秒
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《Journal of Nuclear Science and Technology》2013,50(5):280-286
This report deals with an experiment on the heat transfer of liquid sodium, with particular reference to the effects brought by the application of a magnetic field on pool boiling. The test section, a heater pin of 6.5 mm diameter, was inserted vertically into the center of a sodium tank. The heating surface of the pin was parallel to the magnetic field as well as to the direction of gravity. Under conditions of natural convection in a magnetic field, a sharp rise of the heating surface temperature was always seen to occur at some point when the heat flux was gradually increased, accompanied by the onset of sharp temperature oscillations. The surface superheat required for the initiation of boiling decreased with increasing intensity of the applied magnetic field, reached a minimum, then increased again. The surface temperature fluctuations in nucleate boiling was higher under magnetic field than when free of such influence. The critical heat flux for burn-out was not appreciably affected by magnetic field. 相似文献
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《Journal of Nuclear Science and Technology》2013,50(5):409-414
Stagnant liquid lithium contained in a vertically 1.3 m long and 46 mm I.D. 316-SS cylindrical vessel up to a 0.3 m level was heated by a concentrically inserted heater pin of 12.5 mm O.D. and 54 mm active length. The parallel magnetic field to the vessel was imposed by a superconducting magnet. The experiment covered the ranges of the lithium temperature: 320~510°C, the heat flux: 10~40 W/cm2, the transverse B: 0~1.2 T (Ha = 0~2,730) and the parallel B= 0~3T (Ha = O~6,860). The temperature fluctuation is enhanced by imposing a weak magnetic field of B = 0.1 ~ 0.3 T for both parallel and transverse fields and almost completely suppressed with increasing to B = 1 T in the case of the transverse field but its low frequency component still remains large, becoming oscillatory, up to B = 3 T in the case of parallel field. The heat transfer shows a similar trend to the temperature fluctuation. It increases singularly by a weak B especially in the perpendicular sector to the transverse magnetic field and decreases with increasing B. In the case of parallel magnetic field, the heat transfer increases in a weak field of B = 0.1 ~ 0.5 T, the same as in the transverse magnetic field, but it does not decrease so much in a strong field of B = 1~3 T, presenting a rather higher value than in B = 0 T. 相似文献
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Koichi Hata Yuto Takeuchi Katsuhiko Hama Masahiro Shiotsu 《Journal of Nuclear Science and Technology》2013,50(2):214-227
Natural convection heat transfer coefficients on two parallel horizontal test cylinders in liquid sodium were obtained experimentally and theoretically for various setting angles, γ, between vertical direction and the plane including both of these cylinders’ axes, over the range of 0°–90°. Both test cylinders are 7.6 mm in diameter and 50 mm in heated length with the ratio of the distance between each cylinder axis to the cylinder diameter, S/D, of 2. Theoretical equations for laminar natural convection heat transfer from the two horizontal cylinders were numerically solved for the same conditions as the experimental ones. The average Nusselt numbers Nu on the cylinders obtained experimentally were compared with the corresponding theoretical values on the Nu versus modified Rayleigh number Rf [= Gr*Pr2/(4?+?9Pr1/2?+ 10Pr)] graph. The experimental values of Nu for the upper cylinder are about 20% lower than those for the lower cylinder at γ = 0° for the range of Rf tested here. The value of Nu for the upper cylinder becomes higher and approaches that for the lower cylinder with the increase in γ over the range of 0°–90°: the values for each cylinder agree with each other at γ = 90°. The values of Nu for the lower cylinder at each γ are almost in agreement with those for a single cylinder. The theoretical values of Nu on two cylinders except those for Rf < 4 at γ = 0° are in agreement with the experimental data at each γ with the deviations less than 15%. Correlations for two cylinders were obtained as functions of S/D and γ based on the theoretical solutions. A combined correlation for multi-cylinders in a vertical array based on the correlations for two cylinders was developed. The values by the correlation agree with the theoretical solution for the multi-cylinders for Rf ranging from 4.7 to 63 within 10% difference. 相似文献
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Koichi Hata Yuto Takeuchi Katsuhiko Hama Masahiro Shiotsu 《Journal of Nuclear Science and Technology》2013,50(3):342-354
Natural convection heat transfer from horizontal rod bundles in Nxm × Nym arrays (Nxm, Nym = 5–9) in liquid sodium was numerically analyzed for three types of the bundle geometry (in-line rows, staggered rows I and II). The unsteady laminar two-dimensional basic equations for natural convection heat transfer caused by a step heat flux were numerically solved until the solution reaches a steady state. The PHOENICS code was used for the calculation considering the temperature dependence of thermophysical properties concerned. The surface heat fluxes for each cylinder were equally given for a modified Rayleigh number, Rf, ranging from 0.0637 to 63.1 (q = 1×104 to 7×106 W/m2). Sx/D and Sy/D for the rod bundle, which are the ratios of the distance between center axes on the abscissa and the ordinate to the rod diameter, respectively, were ranged from 1.6 to 2.5 on each bundle geometry. The spatial distribution of Nusselt numbers, Nu, on horizontal rods of a bundle was clarified. The average value of Nusselt number, Nuav, for three types of bundle geometry with various values of Sx/D and Sy/D were calculated to examine the effect of the array size, S/D and Rf on heat transfer. The bundle geometry for the higher Nuav value under the condition of Sx/D×Sy/D = 4 was examined by changing the ratio of Sx/Sy. A correlation for Nuav for the three types of bundle geometry above mentioned including the effects of Sx/D and Sy/D was developed. The correlation can describe the theoretical values of Nuav for the three types of bundle geometry in Nxm × Nym arrays (Nxm, Nym = 5–9) for Sx/D and Sy/D ranging from 1.6 to 2.5 within 10% difference. 相似文献
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利用三维流场计算程序PHOENICS 3 2研究了水平布置干式乏燃料贮存罐内的自然对流传热特性 ,将计算结果与文献的实验数据及计算结果进行了对比分析 ,符合较好。采用同样的布置方式及 2 0 0MW低温供热堆燃料组件的结构及余热功率参数 ,分别采用氮气及水作为工质进行了计算 ,以研究乏燃料贮存罐应用于低温供热堆的可能性。从计算结果中还发现水作为工质的换热效率比氮气高 相似文献
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《Journal of Nuclear Science and Technology》2013,50(7):582-593
For providing background information on the liquid metal cooling of fusion reactors, the MHD effects on heat transfer of flowing lithium was experimentally studied with an emphasis on temperature fluctuations. The test section was constituted of a 15.8 mm I.D., 1.65 mm thick, 316-SS tubing and a 7.6 mm O.D. heater pin with nine 0.5 mm thermocouples. The experiment covered the range of B=0–1.0 T, U=0.2–4.0m/s, T=320–390°C and q=0–68 W/cm2. The results are summarized as follows: (1) With increasing magnetic flux density B, Nusselt number Nu decreases to a value of flat flow velocity model: 6.38 but rises in B=0.1–0.4T. (2) The RMS of temperature fluctuation has strong dependence on B and presents a peak near B=0.25T. (3) The singular rise of Nu is inferred to result from enhanced turbulence due to steepening of radial gradient of velocity near the wall as a result of MHD effect. (4) The transit velocity estimated from temperature cross-correlation in the parallel sector coincides with the mean velocity when B=0 but deviates toward a lower value with applying B. (5) Local flow velocity is decelerated in the magnetically-parallel sectors and accelerated in the perpendicular. 相似文献
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《Journal of Nuclear Science and Technology》2013,50(9):890-900
In readiness for utilization as material for the first wall of fusion reactors that will simultaneously generate high heat flux and a high magnetic field, the heat transfer and melting behavior of stainless steel has been numerically analyzed applying the finite difference method. Envisaging the application of a heat flux of 2.34 kW/cm2 axially on an 8 mm thick, 60 mm diameter stainless steel disk under an axial magnetic field of intensity varied parametrically, the analysis clarifies the effect of differences in applied magnetic field intensity on the configuration of the melted metal zone boundary, on the flow pattern of convective circulation generated within the same zone, and on the radial temperature distribution across the zone. The analysis is performed both for the cases of natural convection alone taken into account and of combination with Marangoni convection. As a result, it is shown that, assuming steady state, the surface flow velocity at the point of interest varies with the applied magnetic field intensity approximately in inverse proportion to the square of Hartmann number in the case of natural convection alone, and that the same applies to the case of combination with Marangoni convection, though with greater deviation from the foregoing analytical result toward higher magnetic field intensities. It is also shown that the assumption of steady state (adopted in deriving the above relation between surface flow velocity and Hartmann number) becomes valid after the lapse of a short time after the start of heat flux application. 相似文献
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基于多孔介质模型,对AP1000非能动余热排出换热器(PRHR-HX)运行初始阶段进行了数值模拟。一回路的入口温度及流量采用RELAP5的计算结果,并以此作为CFD计算的边界条件。采用多孔介质模型处理C型管束区,添加管束区分布阻力。通过商业CFD软件FLUENT计算得到安全壳内置换料水箱(IRWST)侧冷却剂的三维温度及速度分布,通过用户自定义函数UDF完成一回路侧与IRWST侧的耦合换热计算,获得一回路温度分布及换热量。计算结果表明,随着IRWST内冷却剂温度升高,换热器热负荷降低,并出现明显的热分层现象,同时证明采用多孔介质模型与耦合换热计算是分析PRHR/IRWST系统瞬态热工水力特性的有效方法。 相似文献
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本文建立了1∶10的二维钢制安全壳外侧辐射换热和自然对流模型,并用先进流体计算软件Fluent对流场进行计算,得到了完整流道下的速度流场、钢制安全壳上封头顶部的空气速度矢量图,并得出钢制安全壳上封头顶部存在空气滞留区的结论。分析了通道宽度、空气进流速度及壁面黑度对通道换热的影响,结果表明:适当的通道宽度和空气进流速度均能提高通道的换热和换热效率;壁面黑度的提高能明显增强钢制安全壳上封头处的辐射换热。 相似文献
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《Journal of Nuclear Science and Technology》2013,50(10):729-735
In the previous paper, the authors pointed out the motion of bubble or gaseous phase in the direction to the both side walls due to the pinch effect caused by the induced magnetic field in the liquid metal two-phase flow under the strong magnetic field. In the present paper, to clarify the existence of the pinch effect experimentally, an experimental study was performed. Firstly the distributions of the void fraction in the cross section perpendicular to the flow were measured at three locations in the flow direction for the various strength of the applied magnetic field. Secondly a magnetic field was superposed on the induced magnetic field by the outer coil to disturb the pinch effect by the cancel of the induced magnetic field with the superposed one, resulting in the evident redistribution of the void-fraction profile obtained above. From these experiments it is concluded that the pinch effect will play an important role to redistribute the bubble or gaseous phase in the liquid metal two-phase flow under the strong magnetic field and that the effect is more promoted with increasing magnetic interaction number defined as a ratio of the electromagnetic force to the inertia of the fluid. 相似文献
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大功率先进压水堆IVR有效性评价中熔池换热研究 总被引:2,自引:2,他引:0
熔融物堆内滞留-压力容器外部冷却(IVR-ERVC)是一种重要的核电厂严重事故缓解措施。当前针对IVR有效性评价的方法主要是基于集总参数模型对下封头熔池换热进行分析。在大功率先进压水堆熔池集总参数法计算中,堆芯重量变大、压力容器尺寸增加会导致熔池自然对流换热中的瑞利数Ra ′增大。通过使用集总参数分析程序,对比研究熔池氧化层各换热模型的适用范围,计算大功率先进压水堆高瑞利数条件下稳态熔池的自然对流换热,模拟两层稳态熔池模型中压力容器外壁面的热流密度分布,对其进行选定严重事故序列下的IVR-ERVC有效性评价,并对堆内构件设计提出建议。 相似文献
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《Journal of Nuclear Science and Technology》2013,50(1):47-52
The relation between exposure rate and energy loss of secondary electrons in the sensitive volume of a plastic wall counter was derived. The possibilities presented by a proportional counter for use in dosimetry were examined for the case of a combination of polyethylene wall and methane gas. Absolute measurement was found possible by calibration of the observed pulse-height distribution. It was also shown that low exposure rates could be effectively measured with counters provided with small sensitive volume. The characteristics of the counter when used as dosimeter proved very close to those of an ionization chamber. 相似文献
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《Journal of Nuclear Science and Technology》2013,50(10):788-790
A three-dimensional nuclear and thermo-hydrodynamic kinetics calculation code IBIS has been developed, envisaging the treatment of asymmetrical reactivity changes in a large fast breeder reactor. An example of calculation with this code is described, which reveals a difference of void propagation behavior, following a local disturbance, between homogeneous and heterogeneous cores, ascribable to the presence, in the latter case, of inner blanket layers, which act as barrier against void propagation. Of the two parameters of power-to-flow ratio and space-time variation in thermal power, the latter is the more influential on void propagation, and this makes it essential to perform three-dimensional space-dependent kinetic analysis for adequately simulating local perturbations in a heterogeneous core. 相似文献
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建立了非能动余热排出热交换器(PRHR HX)及内置换料水箱(IRWST)分离效应缩比实验系统,研究了PRHR HX排出堆芯余热过程中,单相自然对流阶段及两相池式沸腾阶段下的传热特性,并采用实验数据评价了传统经验关系式在预测PRHR HX缩比模型特殊C型传热管束时的适用性。实验结果表明,在PRHR HX余热排出过程中,IRWST内出现明显热分层现象。对于PRHR HX竖直管束自然对流、池式沸腾传热,传统经验关系式预测值均较为保守;对于下部水平管束,自然对流阶段推荐Churchill自然对流传热公式,池式沸腾阶段推荐Rohsenow经典池式沸腾传热公式;上部水平管束由于受到流体浮升、气泡扰动等因素的附加影响,在自然对流阶段及池式沸腾阶段的传热效果均优于下部水平管束。 相似文献