Thermohydraulics of a single-phase coolant In natural circulation in a reactor

A.Ya. Blagoveshchenskii; V.L. Leonteva; V.N. Mityukov

首页> 外文期刊>Applied Energy >Thermohydraulics of a single-phase coolant In natural circulation in a reactor

【24h】

Thermohydraulics of a single-phase coolant In natural circulation in a reactor

机译：反应堆自然循环中的单相冷却剂的热工水力

获取原文

获取原文并翻译 | 示例

掌桥外文数据库（机构版） >>

开具论文收录证明 >>

文献代查 >>

页面导航

摘要
著录项
相似文献
相关主题

摘要

Conditions are considered for coolant stratification in a VVER reactor system, and experiments are reported together with a model for the temperature distribution in the stratified volume.

机译：在VVER反应器系统中考虑了冷却剂分层的条件，并报告了实验以及分层体积中温度分布的模型。

著录项

来源
《Applied Energy》 |1999年第3期|p.116-120|共5页
作者
A.Ya. Blagoveshchenskii; V.L. Leonteva; V.N. Mityukov;
展开▼
作者单位

展开▼
收录信息
原文格式 PDF
正文语种 eng
中图分类能源与动力工程;
关键词

相似文献

外文文献
中文文献
专利

1. The Power Operating Conditions of the Reactor Installation for a VVER-1000 Reactor with Natural Circulation of the Coolant [J] . A. Ya. Blagoveshchenskii, S. M. Bor, M. N. Konovich, Thermal engineering . 2004,第2期

机译：具有冷却剂自然循环的VVER-1000反应堆的反应堆装置的功率运行条件
2. Multi parameters effect on thermohydraulic instability in natural circulation boiling water reactor during startup [J] . Muhammad Hadid SUBKT, Masanori ARITOMI, Noriyuki WATANABE, JSME International Journal. Series B, Fluids and Thermal Engineering . 2004,第2期

机译：自然循环沸水堆启动过程中多参数对热工水力不稳定的影响
3. Transport Mechanism of Thermohydraulic Instability in Natural Circulation Boiling Water Reactors during Startup [J] . M. Hadid SUBKI, Masanori ARITOMI, Noriyuki WATANABE, Journal of nuclear science and technology . 2003,第11期

机译：自然循环沸水反应堆启动过程中热工水力不稳定的传输机理
4. THERMOHYDRAULIC ANALYSES OF TR-2 RESEARCH REACTOR FOR FORCED CONVECTION AND NATURAL CIRCULATION [C] . SADi KAYA, HASBi YAVUZ Jahrestagung Kerntechnik 2004: annual meeting on nuclear technology 2004: tagungsbericht proceedings . 2004

机译：TR-2强制对流和自然循环研究反应器的热力学分析
5. Thermohydraulic and nuclear modeling of natural fission reactors. [D] . Viggato, Jason Charles. 2004

机译：天然裂变反应堆的热工和核模型。
6. Development of an automatedchemistry control system forsecondary coolant circuits inCANDU nuclear power reactors [O] . J. R. Dean, R. B. Stewart 1979

机译：开发自动化化学控制系统二次冷却液回路坎杜核电反应堆
7. Single-Phase Natural Circulation in a PWR during a Loss of Coolant Accident [O] . Mohammed W. Abdulrahman, Mikdam M. Saleh, Jonathan Anand 2020

机译：在冷却液事故中的PWR中单相自然循环
8. Natural Circulation Cooling During a Small-Break Loss-of-Coolant Accident in a Simulated Pressurized Water Reactor [R] . Loomis, G. G. , Larson, T. K. , Streit, J. E. 1987

机译：模拟加压水反应堆中小断裂失水事故期间的自然循环冷却

Thermohydraulics of a single-phase coolant In natural circulation in a reactor

摘要

著录项

相似文献

相关主题

期刊订阅