搜索结果: 1-6 共查到“核科学技术 coolant”相关记录6条 . 查询时间(0.046 秒)
Comparative Evaluation of Coolant Mixing Experiments at the ROCOM, Vattenfall, and Gidropress Test Facilities
ROCOM Vattenfall Gidropress Test Facilities
2009/9/3
Coolant mixing is an important mitigative mechanism against reactivity accidents caused by local boron dilution. Experiments on coolant mixing were carried out at three different test facilities repre...
Thermal-Hydraulic Analysis of Coolant Flow Decrease in Fuel Channels of Smolensk-3 RBMK during GDH Blockage Event
Thermal-Hydraulic Coolant Flow
2009/9/3
One of the transients that have received considerable attention in the safety evaluation of RBMK reactors is the partial break of a group distribution header (GDH). The coolant flow rate blockage in o...
Dynamic Analysis of Coolant Channel and Its Internals of Indian 540 MWe PHWR Reactor
Coolant Channel Indian 540 MWe PHWR Reactor
2009/9/3
The horizontal coolant channel is one of the important parts of primary heat transport system in PHWR type of reactors. There are in all 392 channels in the core of Indian 540 MWe reactor. Each ...
International Standard Problems and Small Break Loss-of-Coolant Accident (SBLOCA)
International Standard Problems SBLOCA
2009/9/3
Best-estimate thermal-hydraulic system codes are widely used to perform safety and licensing analyses of nuclear power plants and also used in the design of advance reactors. Evaluation of the capabil...
Effect of Coolant Inventories and Parallel Loop Interconnections on the Natural Circulation in Various Heat Transport Systems of a Nuclear Power Plant during Station Blackout
the Natural Circulation Various Heat Transport Systems
2009/9/3
Provision of passive means to reactor core decay heat removal enhances the nuclear power plant (NPP) safety and availability. In the earlier Indian pressurised heavy water reactors (IPHWRs), like the ...
600MW反应堆冷却剂系统主管道安装监理（The Installation Techniques and Supervision for 600MW Reactor Coolant Piping ）
秦山二期 反应堆冷却剂系统 主管道
2008/10/22
论述了秦山核电二期工程600 MW反应堆冷却剂系统主管道的安装、焊接技术及监理要点，并对反应堆冷却剂系统主管道的安装顺序、安装技术要求、焊接质量检验方法以及焊接变形的控制等方面给予了详细的阐述，对核电站反应堆冷却剂系统主管道安装焊接的质量控制具有借鉴作用。