Critical heat flux at low pressures and flow rates

被引：0

作者：

Sergeev, V.V. ^{[1
]}

Smirnov, A.M. ^{[1
]}

Gal'chenko, E.F. ^{[1
]}

Krylov, D.A. ^{[1
]}

机构：

[1] GNTs Fiziko-Energeticheskij Inst, Obninsk, Russia

来源：

Atomnaya Energiya | 1995年 / 79卷 / 01期

关键词：

Critical heat flux;

D O I：

暂无

中图分类号：

学科分类号：

摘要：

Results of experimental investigations are presented of the critical heat flux in conditions of the upward water flow at a low pressure in a circular tube with the internal diameter of 11 mm and in a 19 fuel rod cluster in the WWER reactor geometry. The experiments are carried out at the output pressure of 0.1-1.1 MPa, the mass flow rate of 25-500 kg/(m2&middots), the input water temperature of 9-50°C and at the input throttling up to 5 MPa. Experimental data are compared with data calculated by means of the RELAP5/mod3 code. It is found that the calculational data exceed essentially the experimental ones.

引用

页码：3 / 7