1、

The hybrid breeders can provide plenty of fissile material for PWR or FBR.

聚变-裂变混合堆可以为压水堆或快堆提供充足的核燃料.

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2、

There exists probability of fuel assembly damage in PWR during refueling period.

在压水堆核电站换料的过程中存在燃料棒破损的可能.

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3、

This paper described benchmark test noise si-gnal analysis of PWR and gets some useful results.

本文介绍了压水堆噪声基准试验信号分析,并从中得出一些有用的结果。

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4、

This paper studied the modeling and controlling of PWR and developed simulation software as well.

本文以大型压水堆核电站为对象,研究了核电站的建模控制以及仿真软件的开发.

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5、

Presented is a model for the multi region and variable node PWR core.

建立了多区变节点压水堆堆芯的数学物理模型.

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6、

A real time model of simulation of secondary system for PWR nuclear power unit is presented.

介绍了核电机组二回路主蒸汽与给水回热系统实时仿真.

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7、

The Important Characteristic of KWU PWR Nuclear Power Plant& Application of the Limitation System

KWU压水堆核电站重要特点&限制系统在设计中的应用

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8、

This paper summaries the function and advantage of the limitation system of KWU PWR nuclear power plant.

本文概述KWU压水堆核电站限制系统的功能和优点。

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9、

Scheme B in the article, i.e. a method of using the rebuilt used fuel from PWR to replace the natural uranium fuel for HWR, was discussed.

并对如何使用此再制的核燃料提出两种方案,分别适用于压水堆和以天然铀为燃料的坎杜重水堆。

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10、

Selection of Emergency Release Source Term and Partition of EPZ in the Chinese PWR NPP

压水堆核电站应急源项的选定和应急计划区的划分

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11、
12、

Considering the function of PWR primary loop system, an architecture and federations design of primary loop system operation and control simulation based on High Level Architecture ( HLA) is presented. M?

在对压水堆主回路系统分析的基础上,设计了基于高层体系结构(HLA)的主回路系统仿真的联邦成员构成和实现主回路系统虚拟仿真的体系结构。

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13、

Control rods are used in a PWR typically to change the power level and also to shut down the reactor.

控制棒是在一个加压水冷却反应堆里使用的,用来改变能量的级别,也可以用来停止反应堆。

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14、

There are four types for PWR pressure-relieving devices: direct acting safety valve, pilot-operated pressure relief valve, power-operated pressure relief valve and safety valve with auxiliaries.

PWR的压力释放装置主要有四种类型:直接作用式安全阀、先导操作压力释放阀、动力作用式压力释放阀和具有辅助装置的安全阀。

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15、

Casting duplex stainless steels for primary coolant loop in PWR is safe during the service life of 40 years.

保守估计核电一回路管道用铸造双相不锈钢在预定的服役时间40年内是安全的。

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16、

The drive is different from electric-magnetic drive for PWR or hydraulic drive for BWR.

这种传动不同于压水堆上使用的电磁 - 机械传动,也不同于沸水堆上使用的液压传动.

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17、

The comparison of the computational results for reactor core of PWR and BWR are also presented.

文中还给出了压水堆和沸水堆堆芯计算实例的比较.

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