Current state of system thermohydraulic codes and trends in their development abroad

被引：10

作者：

Asmolov, V. G. ^{[1
]}

Blinkov, V. N. ^{[1
]}

Melikhov, V. I. ^{[1
]}

Melikhov, O. I. ^{[1
]}

Parfenov, Yu. V. ^{[1
]}

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

Kiselev, A. E. ^{[2
]}

Dolganov, K. S. ^{[2
]}

机构：

[1] Natl Res Univ Moscow, Power Engn Inst, Moscow, Russia

[2] Russian Acad Sci, Nucl Safety Inst, Moscow, Russia

来源：

HIGH TEMPERATURE | 2014年 / 52卷 / 01期

基金：

俄罗斯基础研究基金会;

关键词：

GENERATION;

D O I：

10.1134/S0018151X14010027

中图分类号：

O59 [应用物理学];

学科分类号：

摘要：

The current tendencies in development of the system thermohydraulic codes for analysis of emergency processes in nuclear reactor cooling systems abroad are considered. The main trends towards improvement of physical models, numerical methods, and the code architecture and their validation are reported. Works on the techniques for evaluation of the uncertainty of the calculation results obtained using the thermohydraulic codes are listed.

引用

页码：98 / 109

页数：12

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[1] Current state of system thermohydraulic codes and trends in their development abroad
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V. N. Blinkov
V. I. Melikhov
O. I. Melikhov
Yu. V. Parfenov
D. A. Emelyanov
A. E. Kiselev
K. S. Dolganov
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