首页> 外文会议>The 13th International Conference on Nuclear Engineering: Abstracts >THE EFFECT OF RISER CONDENSATION ON THE TWO-PHASE FLOW STABILITY
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THE EFFECT OF RISER CONDENSATION ON THE TWO-PHASE FLOW STABILITY

机译:冒口冷凝对两相流稳定性的影响

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摘要

A one-dimensional analytical model has been developed tornbe used for the frequency domain linear analysis of density-wavernoscillations in CAREM-25 nuclear reactor prototype.rnThe natural circulation loop is divided into a single-phasernand a two-phase region. The two-phase region is representedrnby the drift-flux model. The model accounts for aphasic sliprnand subcooled boiling. The exact equation for the total looprnpressure drop is perturbed around the steady state. Thernstability characteristics of the loop are investigated using thernroot finding method. The marginal stability boundary (MSB)rnis determined in the two-dimensional thermodynamicrnequilibrium space parameters, the subcooled boiling numberrnand the phase change number ,plane. The flow instabilityrnregions are appeared at low and high core power. In the lowrnheat flux range, the trends of the thermal equilibrium - equalrnvelocity (homogeneous) model and the thermal nonrnequilibrium - non equal velocity model are the same becausernthe steam quality is small. In the high heat flux range, (a)rnfrom high subcooled boiling number to reaching a criticalrnvalue, the steam quality calculation of the first model isrngreater and has the effect of stabilizing the system more thanrnthe second one, (b) from the critical value to low subcooledrnboiling number, the two-phase region length calculation ofrnthe first model is smaller and has the effect of stabilizing thernsystem less than the second one. As the inlet restriction andrnthe riser condensation are increased, the model predicts a more stable system, the stable region is broadened at allrnpower ranges. As the exit restriction is decreased and thernsystem pressure is increased, the model predicts a morernstable system, the stable region is shifted to the right.
机译:建立了一维分析模型,用于CAREM-25核反应堆原型密度波振荡的频域线性分析。自然循环回路分为单相和两相区域。两相区域由漂移通量模型表示。该模型考虑了无相滑移和过冷沸腾。总回路压降的精确方程在稳态附近受到干扰。使用rnroot查找方法研究回路的热稳定性特征。由二维热力学平衡空间参数,过冷沸腾数和相变数平面确定边际稳定性边界。流动不稳定性区域出现在低核心功率和高核心功率下。在低热通量范围内,由于蒸汽质量差,热平衡-等速(均质)模型和热非平衡-非等速模型的趋势相同。在高热通量范围内,(a)从高过冷沸腾数到达到临界值,第一个模型的蒸汽质量计算会提高系统的稳定性,并且比第二个模型更能使系统稳定,(b)从临界值到低过冷沸腾数,第一个模型的两相区域长度计算较小,并且具有比第二个模型稳定系统的效果。随着入口限制和立管冷凝水的增加,该模型预测系统会更稳定,在所有功率范围内,稳定区域都会扩大。随着出口限制的减少和系统压力的增加,该模型预测系统更加稳定,稳定区域向右移动。

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  • 会议地点 Beijing(CN)
  • 作者单位

    Centro Atomico Bariloche, Bariloche, Rio Negro,rnArgentinarnPhone: 54-2944-445101, Fax: 54-2944-445299rnE mail: abdouh@cab.cnea.gov.ar;

    INVAP S.E., Bariloche, Rio Negro, ArgentinarnPhone: 54-2944-445400, Fa x: 54-2944-445416rnE mail: garea@invap.com.ar;

    Universidad Argentina de la Empresa, Bounos Aires, ArgentinarnPhone: 54-114-3797496, Fax: 54-114-3797495rnE mail: alarreteguy@uade.edu.ar;

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  • 正文语种 eng
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  • 入库时间 2022-08-26 14:02:01

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