loca
英
美 [ˈloʊkə]
n. 轨迹; 中心
复数：locas
双语例句
- And you do have a high pressure coolant injection system that could also be called in to address breaks that perhaps are not as a large as a main LOCA.
你有一个高压的冷却剂注入系统，也也能使用来处理，破裂，破裂可能不和一个失水事故一样大。 - Loca stress analysis of anchorage zone saddle of part cable-stayed bridge
部分斜拉桥鞍座锚固区局部应力分析 - She's so La Vida loca.
她真的很神经耶。 - And he continues to sing and act?@ Livin 'La Vida Loca.
他仍在继续的唱并演着？？Livin'LaVidaLoca。 - The characteristics of large break loss of coolant accident ( LOCA) for Xi'an Pulsed Reactor were analyzed.
失水事故是核电站设计的基准事故之一，是压水堆事故分析关注的重点。 - His song "Living La Vida Loca" is the biggest selling No. 1 single in the history of Columbia Records.
他的歌曲生活在疯狂世界中成为哥伦比亚唱片公司历史上销量最好的单曲。 - Based on GO-FLOW methodology, the reliability of emergency core cooling system ( ECCS) in lose of coolant accident ( LOCA) was analyzed.
应用GO-FLOW法分析在失水事故过程中紧急堆芯冷却系统的可靠性。 - The momentum integral method is applied in the frame of safety analysis of pressure water reactors under hypothetical loss of coolant accident ( LOCA) conditions to simulate numerically film condensation, rewetting and vaporization on the inner surface of a pressure water reactor containment.
采用动量积分方法分析压水堆发生失水事故时在安全壳的内表面上的液膜凝结、再浸润和蒸发过程。 - This paper describes the nonlinear dynamic analysis procedure of reactor system including the engineering method for nonlinear factors, the establishment of the nonlinear dynamic model and the nonlinear dynamic analysis method. The generation and the application of the LOCA dynamic response for the system are also presented.
文中着重介绍了反应堆系统中非线性因素的工程处理方法、非线性动力分析模型的建立和非线性动力分析方法，对于系统LOCA动力响应及其在设计中的应用也作了简要叙述。 - The application of trac-pf1 to the analysis of large break loca
TRAC-PF1在大破口LOCA分析中的应用 - Simulation of LOCA in the auxiliary primary loop system of nuclear power plant
核动力装置一回路辅助系统失水事故的仿真研究 - A new advanced calculation model ( True Core Uncovered Model) of LOCA of PRC-II Reactor and the relevant code ( MCRLOCA) are first put forward.
在失水事故分析中首次提出了一种新的、先进的计算模型（真实堆芯裸露模型）和计算机程序（MCRLOCA）。 - Introduction of DRM for Large Break LOCA Analysis
大破口失水事故的DRM分析方法介绍 - Research on Reactor Dynamic Analysis under Seismic and LOCA Conditions
核反应堆地震和失水事故下结构动力分析研究 - Experiment result is significant for safe operation of nuclear heating reactor and security analysis program to confirm small break LOCA.
实验结果对核供热堆的安全运行及验证小破口事故安全分析程序有重要意义。 - The Linear Dynamic Response Analysis on a Core Barrel under the LOCA Condition in Primary Piping
主管道失水事故时吊篮动态响应线性分析 - From the developing of Large Break LOCA analysis method, this paper introduces the French DRM ( Deterministic Realistic Methodology) used for Large Break LOCA.
从大破口失水事故分析方法的发展过程，阐述了法国大破口失水事故分析方法DRM。 - The LOCA of representative location of auxiliary primary loop system in nuclear power plant is simulated with an easily manipulative and quickly calculative tool software.
运用一种操作简便、计算速度快的工具软件对某核动力装置一回路辅助系统典型位置的失水事故进行了仿真。 - The details of dynamic response analysis for reactor and steam generator under LOCA and seismic loading were performed.
对堆本体和蒸汽发生器在失水事故和地震载荷下的动态响应作了详细的分析。 - Experiment study on small break LOCA of nuclear heating reactor
核供热堆小破口事故实验研究 - The detail dynamic analysis and evaluation for the reactor internals, control rod drive system, fuel assemblies and the steam generator tubes, under combined application of the earthquake and LOCA loads, are the requirements of design codes and safety review.
对反应堆堆内构件、控制棒驱动系统、燃料组件和蒸汽发生器传热管等设备进行地震加失水事故联合作用下详细的动力分析与评定，是核电厂设计规范和安全审查的要求。 - The study on flow and heat transfer in downcomer under loss of coolant accident ( LOCA) is important to the safety of reactor pressure vessel ( RPV).
失水事故工况（LOCA）下反应堆下降环腔内的流动和传热研究，对反应堆压力容器（RPV）的安全具有重要的意义。 - The trip accident ofexternal power supply, reactivity accident and small break LOCA are simplyanalysed.
对全厂断电事故、反应性事故和小破口失水事故进行了初步分析。 - The mass flowrate and steam quality measuring of two phase flowrate is an essential issue in the tests of loss-of-coolant accident ( LOCA).
两相流质量流量和质量含汽率的测量是反应堆失水事故试验的重要课题。 - The analysis and checking calculation of LOCA simulating test in an advanced thermal reactor
新型转换堆失水事故模拟实验的验算和分析 - Research on reactor dynamic analysis under seismic and LOCA conditions has been fulfilled. It includes transient discharging loading analysis for reactor and steam generator under LOCA condition, dynamic response analysis for reactor structures, and dynamic response analysis and evaluation for fuel assembly structures.
对核反应堆在地震和失水事故下结构动力分析开展了研究，包括反应堆和蒸汽发生器在失水事故下的瞬态卸压载荷分析研究、反应堆结构动力响应分析研究和燃料组件动力响应分析评定研究。 - Dynamic Response Analysis for Fuel Assemblies under Earthquake and LOCA Accidents
燃料组件在地震和失水工况下的结构动力反应分析 - This article gives a brief description of the features of TRAC-PF1 in connec-tion with the analysis of a large break LOCA.
文章简述了TRAC-PF1与大破口LOCA分析有关的功能和特点。 - Finally, numerical simulation demonstrated the different effects of different algorithm parameters on the loca of particle position and particle velocity, and further illustrated the validity of conclusions given in this paper.
数值仿真实验展示了不同子区域内的算法参数对粒子位置和粒子速度运动轨迹的不同影响，进一步验证了所得结论的正确性。 - At present, the LOCA analysis method used in China is conservative, while the realistic method used for considerable Nuclear Power Plants ( NPPs) overseas, such as best estimate plus uncertainty ( BEPU) method.
目前我国的核电厂（NPPs）LOCA分析仍采用保守分析方法，而国外已经有相当一部分核电厂采用了现实LOCA（如最佳估算+不确定性，BEPU）分析方法。