The size and number of thermocouples in a infrared silicon based thermopile device have much effect on the performance of the devices in the non contact infrared temperature measurement.
分析了多晶硅 -金集成热堆中热电偶的尺寸和对数对热堆性能的影响 ,对非接触红外测温的实用型热堆提出了设计和改进的思路 。
Design of infrared thermopiles with heat reflective emitter coatings;
覆盖热反射层的红外热电堆改进设计
Self-made Thermopile Heat Flow Meter in Detection of Construction Thermal Performance;
自制热电堆型热流计及其在建筑热工检测中的应用
CMOS Compatible MEMS P/N Polycrystalline Silicon Thermopile IR Detector;
CMOS兼容的微机械P/N多晶硅热电堆红外探测器
Thermal hydraulic performance of seawater desalination system using a nuclear heating reactor;
核供热堆海水淡化系统的热工水力学特性
Study on Software System of PC-Based Simulator(PCNHR)for 200MW Nuclear Heating Reactor;
基于微机的核供热堆模拟器PCNHR1.0的软件系统研究
Dynamic analysis of nonlinear model of 200MW nuclear heating reactor;
200 MW核供热堆非线性模型的动态分析
The hydraulic system of control rod drives is one of the key systems in a nuclear heating reactor.
控制棒水力驱动系统是核供热堆的关键系统之一 ,其运行失效将直接导致供热堆的非计划停堆。
The nuclear heating reactor has inherent safety with very simple structures, so it can be used as minitype nuclear powered equipment.
用扩容蒸发器来代替传统的蒸汽发生器 ,不但使供热堆系统得到了极大的简化 ,而且系统的安全性和可靠性也得到了提高 ,比较适合用作舰船上的小型核动力装置。
Thermopile is usually a blackened thermal detector.
热堆一般是个涂黑了的热探测器。
A soft-measuring method to measure the core coolant temperature at the outlet of a nuclear heating reactor
核供热堆堆芯冷却剂出口温度的软测量方法
The Nuclear Core Design of 450MWt Pressurized Water Reactor
45万千瓦(热)压水堆堆芯核设计
Heat Balance Test for Determined Reactor Core Power
计算核反应堆堆芯功率的热平衡试验
fast reactor thermal engineering facility
快堆热工程研究设施
laser controlled thermonuclear reactor
激光受控热核反应堆
space thermionic auxiliary reactor
空间热离子辅助反应堆
advanced thermal reactor
改进型热中子反应堆
advanced epithermal thorium reactor
改进型超热钍反应堆
STR (submarine thermal reactor)
潜艇用热中子反应堆
core spray heat exchanger booster pump
堆芯喷淋热交换讫压泵
international thermonuclear experimental reactor
国际热核实验反应堆
Green hay heats in a mow.
青草在草堆中会发热。
Self-made Thermopile Heat Flow Meter and Testing of Error Analysis
热电堆型热流计制作及测试误差分析
TRANSIENT BEHAVIOR OF THE LOSS OF HEAT SINK WITHOUT SCRAM AND INHERENT SAFETY OF SODIUM COOLED FAST REACTOR
钠冷快堆无停堆保护失热阱固有安全特性
The heat dissolved the candles into opaque pools of wax
热使这些蜡烛融化成了一堆堆不透明的蜡液。
A THERMAL-HYDRAULIC MODEL FOR BWR SIMULATORS
沸水堆堆芯模拟程序中的热工-水力模型
A Measurement Method Regarding Reactor Core Thermal Power and Error Analysis
反应堆堆芯热功率测量方法及其误差分析
