The present state and development of Russian systems of thermohydraulic codes for simulating emergency and transient processes in nuclear power stations with VVER reactors

被引：0

作者：

Nigmatulin, B.I. ^{[1
]}

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

Solov'ev, S.L. ^{[1
]}

机构：

[1] Ministry of Nuclear Energy of RF, ul. Bol'shaya Ordynka 24/26, Moscow, 101000, Russia

来源：

Teploenergetika | 2001年 / 03期

关键词：

Computer simulation - Hydraulics - Nuclear reactor accidents - Pressurized water reactors - Transients;

D O I：

暂无

中图分类号：

学科分类号：

摘要：

The present state and the development of Russian codes for simulating the behavior of all systems at nuclear power stations (NPSs) under transient and emergency conditions are considered. The advantages, the main characteristics, and the capabilities of the code CORSAR recognized as being the base code for developing an advanced systems thermohydraulic code for NPSs with VVER reactors are formulated.

引用

页码：17 / 20

共 24 条

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