Recommendations on selecting the closing relations for calculating friction pressure drop in the loops of nuclear power stations equipped with VVER reactors

被引：2

作者：

Alipchenkov V.M. ^{[1
]}

Belikov V.V. ^{[2
]}

Davydov A.V. ^{[2
]}

Emel'Yanov D.A. ^{[2
]}

Mosunova N.A. ^{[2
]}

机构：

[1] Joint Institute for High Temperatures of the Russian Academy of Sciences, Izhorskaya str., 13 bd. 2

[2] Nuclear Safety Institute of the Russian Academy of Sciences, Bol'shaya Tul'skaya str., 52

来源：

Thermal Engineering | 2013年 / 60卷 / 5期

关键词：

closing relation; mathematical simulation; nuclear power station; thermal-hydraulic computation code; verification; VVER-type reactor; wall friction;

D O I：

10.1134/S0040601513050029

中图分类号：

学科分类号：

摘要：

Closing relations describing friction pressure drop during the motion of two-phase flows that are widely applied in thermal-hydraulic codes and in calculations of the parameters characterizing the flow of water coolant in the loops of reactor installations used at nuclear power stations and in other thermal power systems are reviewed. A new formula developed by the authors of this paper is proposed. The above-mentioned relations are implemented in the HYDRA-IBRAE thermal-hydraulic computation code developed at the Nuclear Safety Institute of the Russian Academy of Sciences. A series of verification calculations is carried out for a wide range of pressures, flowrates, and heat fluxes typical for transient and emergency operating conditions of nuclear power stations equipped with VVER reactors. Advantages and shortcomings of different closing relations are revealed, and recommendations for using them in carrying out thermal-hydraulic calculations of coolant flow in the loops of VVER-based nuclear power stations are given. © 2013 Pleiades Publishing, Ltd.

引用

页码：331 / 337

页数：6

共 20 条

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