Development of a steady thermal-hydraulic analysis code for the China Advanced Research Reactor

被引：3

作者：

Tian W. ^{[1
]}

Qiu S. ^{[1
]}

Guo Y. ^{[1
]}

Su G. ^{[1
]}

Jia D. ^{[1
]}

Liu T. ^{[2
]}

Zhang J. ^{[2
]}

机构：

[1] Department of Nuclear Engineering, Xi'an Jiaotong University

[2] China Institute of Atomic Energy

来源：

Frontiers of Energy and Power Engineering in China | 2007年 / 1卷 / 2期

关键词：

China advanced research reactor; Plate type fuel; Steady-state analysis; Thermal-hydraulic; Unsymmetrical cooling condition;

D O I：

10.1007/s00000-007-0024-8

中图分类号：

学科分类号：

摘要：

A multi-channel model steady-state thermal-hydraulic analysis code was developed for the China Advanced Research Reactor (CARR). By simulating the whole reactor core, the detailed mass flow distribution in the core was obtained. The result shows that structure size plays the most important role in mass flow distribution, and the influence of core power could be neglected under single-phase flow. The temperature field of the fuel element under unsymmetrical cooling condition was also obtained, which is necessary for further study such as stress analysis, etc. of the fuel element. At the same time, considering the hot channel effect including engineering factor and nuclear factor, calculation of the mean and hot channel was carried out and it is proved that all thermal-hydraulic parameters satisfy the Safety design regulation of CARR". © Higher Education Press 2007."

引用

页码：189 / 194

页数：5

共 5 条

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[3]

Sudo Y., Kaminaga M., A new CHF correlation scheme proposed for vertical rectangular channels heated from both sides in nuclear research reactors, Journal of Heat Transfer, 6, 4, pp. 115-426, (1993)

[4]

Sudo Y., Core thermohydraulic design with 20% LEU fuel for upgraded research reactor JRR-3, Journal of Nuclear Science and Technology, 22, 5, pp. 551-562, (1985)

[5]

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