Primary Studies on Factors for Hydrogen Concentration Distribution in Containment under Severe Accidents;
严重事故下安全壳内氢气浓度场分布影响因素的初步研究
PWR containment radiation levels calculation relate to core conditions;
PWR堆芯不同状况下安全壳内辐射水平的计算
Preliminary Analysis of Hydrogen Distribution and Risk under Severe Accident Conditions for QINSHAN NPP Unit 2 Containment;
秦山二期核电厂严重事故下安全壳内氢气浓度分布及风险初步分析
Based on the investigation on accident control,the paper presents a new safety theory and points out that the study and practice of safety management theory are the prerequisite to establish the safety shell.
提出一个新的安全管理概念———安全管理界壳,并运用安全管理界壳分析事故(危害)防御活动的不足,指明加强安全管理理论的研究和实践是构筑持续安全之盾———安全界壳的必由之路。
Modal analysis for a 1∶10 model of CNP1000 reactor containment;
CNP1000安全壳1∶10模型的模态分析
The Research and Implement of Network Security Protocol-SSH;
SSH(Secure Shell),即安全外壳,是一种应用层的安全通信协议。
containment spray injection system
安全壳喷淋注入系统
reactor containment building
反应堆安全壳建筑物
containment spray recirculation system
安全壳喷淋再循环系统
ASEISMIC SAFETY ANALYSIS OF A CONTAINMENT VESSEL MODEL FOR CNP1000 NUCLEAR POWER PLANT
CNP1000核电厂安全壳模型结构抗震安全分析
Electrical penetration assemblies in containment structures for nuclear power plants
GB/T13538-1992核电厂安全壳电气贯穿件
Type exit, to get back to a normal session.
只不过现在它是一个安全壳的对话。
Reactor Containment Decompression and Filtration in Qinshan NPP Phase Ⅱ;
秦山二期安全壳超压后的过滤及卸压
Seismic Analysis of a Reinforced Concrete Containment Vessel on Isolating Devices;
某核电站安全壳的隔震地震反应分析
Containment ventilation radioactivity monitoring of WWER-1000 reactors
WWER-1000堆型安全壳通风放射性监测
Research Advance in Security Protection Performance of Nuclear Power Plant Containment under Exogenous Events
核电站安全壳在外来事件作用下的安全防护性能研究进展
CANDU-6 Reactor Building Integrity Leak Rate Measurement Research;
重水堆安全壳整体密封性能测试技术研究
Numerical Simulation of Hydrogen Distribution within Containment in Severe Accidents;
严重事故下安全壳内氢气分布的数值研究
Construction Technology of Safety Shell Prestress in Ling'ao Nuclear Power Station Phase Ⅱ
岭澳核电站二期核岛安全壳预应力施工技术
Aging Factors of Prestressed Concrete Containment Vessel in Nuclear Power Plant
核电站预应力混凝土安全壳的老化因素研究
Consideration on the Design Improvement of Containment Sump Strainer of NPP in China
国内核电厂安全壳地坑滤网设计改进考虑
AGEING ANALYSIS AND AGEING DETECTING OF CONCRETE CONTAINMENT BUILDINGS FOR NUCLEAR POWER PLANT
核电站安全壳老化机理分析与探测方法
Analysis on Prestressing Losses of Mass Concrete (Safety Shell of Nuclear Power Plant)
大体积混凝土(核电站安全壳)预应力损失分析
The relief valve should be able to be removed by unscrewing the relief valve from the housing.
通过从外壳上旋下安全阀应该能够拆卸安全阀。
