primary coolant

[ˈpraiməri ˈku:lənt]
  • 释义

    一次冷却剂,一次载热剂;

数据更新时间:2025-11-14 06:47:36
1、

Mathematical Model of Primary Coolant in Nuclear Power Plant Influenced by Ocean Conditions

核动力装置一回路冷却剂受海洋条件影响的数学模型

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2、

Numerical simulation and analysis of three-dimensional flow in a primary coolant pump

主冷却剂泵三维流场数值模拟与分析

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3、

The reactor vessel constitutes the main part of pressure boundary of primary coolant.

反应堆压力壳构成了主冷却剂压力边界的主体。

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4、

A new method for continuously monitoring the leakage of the primary coolant into the second circuit in the reactor

连续监测反应堆一回路冷却剂向二回路泄漏的一种新方法

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5、

Fault of primary coolant circuit equipment in nuclear power plant and the comprehensive intelligent diagnosis system

船用核动力一回路设备故障综合智能诊断系统

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6、

Casting Technique for Primary Coolant Piping for Pressurized Water Reactor Power Plant and Its Localization

压水堆一回路管道的铸造工艺及其国产化

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7、

Therefore, the materials for SG heat exchange tubes must meet stringent technical requirements, among which resistance to the corrosion in primary and secondary coolant corrosion is of the greatest concern.

因此,SG传热管用材必须满足苛刻的技术要求,其中最关键的是要满足在PWR运行温度范围内具有良好的抗一、二回路水介质腐蚀的能力。

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8、

In 2010 it ran out of the cryogenic coolant that enabled its primary mission of mapping the skies.

2010年其低温冷却剂消耗殆尽,而低温冷却剂是其绘制星云地图的必备。

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9、

The paper describes the mathematics models of the reactor physic and primary coolant thermal-hydraulics.

建立了描述反应堆与主冷却剂系统的物理、热工水力特性的数学模型.

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10、

The primary heat exchanger ( PHX) is a key heat transmission equipment of the lead alloy cooled reactor, and it is also a safety barrier to prevent the radioactive lead alloy coolant.

主换热器是铅合金冷却反应堆中关键的热传输设备,同时也是防止一回路放射性冷却剂外逸的一道安全屏障,此外,换热器结构设计合理性也将直接影响反应堆安全性及经济性。

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11、

Steam generator ( SG) is one of main equipments in the pressurized water reactor ( PWR) nuclear power plant, but also it is a pivotal equipment which brings heat from reactor core to the secondary loop coolant by primary loop water.

蒸汽发生器是压水堆核动力装置中的主要设备之一,也是把一回路冷却剂从反应堆堆芯带出的热量传给二回路水的关键设备。

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12、

Study on Primary Coolant System Depressurization Effect Factor in Pressurized Water Reactor

压水堆一回路卸压措施影响因素研究

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