An Investigation of Burnout on the Downward Facing Slope Surfaces of the Water-Cooled Components Of a Corium Localizing Device at a Nuclear Power Station With VVER-1000 Reactors

V.K. Efimov; O.D. Chernyi; V.S. Granovskii

首页> 外文期刊>Thermal engineering >An Investigation of Burnout on the Downward Facing Slope Surfaces of the Water-Cooled Components Of a Corium Localizing Device at a Nuclear Power Station With VVER-1000 Reactors

【24h】

An Investigation of Burnout on the Downward Facing Slope Surfaces of the Water-Cooled Components Of a Corium Localizing Device at a Nuclear Power Station With VVER-1000 Reactors

机译：具有VVER-1000反应堆的核电站中钙局部化装置的水冷组件的向下冷却面的燃尽现象研究

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 >>

页面导航

摘要
著录项
相似文献
相关主题

摘要

Experimental investigations of burnout were carried out on a large-scale model of a heat exchanger incorporated in a molten-core localizing device. Dependences showing the critical heat flux at a pressure close to atmospheric as a function of subcooling on the downward faced plate tilted through 8 and 12 deg were obtained.

机译：在组装于熔融芯定位装置中的热交换器的大型模型上进行了燃尽的实验研究。获得了在接近大气压的压力下的临界热通量的依赖性，该临界热通量是在倾斜8度和12度的下面板上过冷的函数。

著录项

来源
《Thermal engineering》 |2001年第9期|p.718-720|共3页
作者
V.K. Efimov; O.D. Chernyi; V.S. Granovskii;
展开▼
作者单位

展开▼
收录信息
原文格式 PDF
正文语种 eng
中图分类发电、发电厂;
关键词

相似文献

外文文献
中文文献
专利

1. The Concept of Localization of the Corium Melt in the Ex-Vessel Stage of a Severe Accident at a Nuclear Power Station With a VVER-1000 Reactor [J] . I.V. Kuhtevich, V.V. Bezlepkin, V.S. Granovskii Thermal engineering . 2001,第9期

机译：带有VVER-1000反应堆的核电站在严重事故前船期中的皮质熔体本地化概念
2. The Device for Core Melt Localization at the Tyan'van Nuclear Power Station with a VVER-1000 Reactor [J] . A.S. Sidorov, A.B. Nedorezov, M.F. Rogov Thermal engineering . 2001,第9期

机译：带VVER-1000反应堆的Tyan'van核电站堆芯熔体定位设备
3. The Interaction of Nuclear Reactor Core Melt with Oxide Sacrificial Material of Localization Device for a Nuclear Power Plant with Water-Moderated Water-Cooled Power Reactor [J] . V. G. Asmolov, A. A. Sulatskii, S. V. Beshta, High temperature: English translation of teplofizika vysokikh temperatur . 2007,第1期

机译：带有水调节水冷动力堆的核电站核反应堆堆芯熔体与定位装置氧化物牺牲材料的相互作用
4. THE CONCEPT AND MAIN SOLUTIONS FOR THE SAFETY OF A NEW RUSSIAN PROJECT OF A NUCLEAR POWER STATION WITH A VVER-1000 REACTOR [C] . G. S. Taranov, V. M. Berkovich International Conference on Nuclear Engineering . 2000

机译：具有VVER-1000反应堆的核电站新俄罗斯项目安全的概念和主要解决方案
5. Analysis of space reactor system components: Investigation through simulation and non-nuclear testing. [D] . Bragg-Sitton, Shannon M. 2004

机译：空间反应堆系统组成部分的分析：通过仿真和无核试验进行调查。
6. Investigating the knowledge and preparedness of proximal residents to a general-emergency event at the Koeberg Nuclear Power Station [O] . Alberto P. Francioli 2016

机译：调查近郊居民在Koeberg核电站发生一般性紧急事件时的知识和准备情况
7. A MATHEMATICAL MODEL OF THE ELECTRICAL ENGINEERING COMPLEX FOR DRIVE OF MAIN CIRCULATION PUMPS OF NUCLEAR REACTOR VVER-1000 OF NUCLEAR POWER PLANTS [O] . K. M. Vasyliv, L. I. Mazurenko 2019

机译：核电站核电厂主循环泵电气工程复合体的数学模型
8. Development of an Automated System of Nuclear Materials Accounting for Nuclear Power Stations with Water-Cooled, Water-Moderated Reactors. Final Report for the Period 1 March 1979 - 29 February 1981 [R] . Babaev, N. S. 1981

机译：用水冷式水冷反应堆开发核电站自动核材料核算系统。 1979年3月1日至1981年2月29日期间的最后报告

An Investigation of Burnout on the Downward Facing Slope Surfaces of the Water-Cooled Components Of a Corium Localizing Device at a Nuclear Power Station With VVER-1000 Reactors

摘要

著录项

相似文献

相关主题

期刊订阅