thermohydraulic

基本解释

The thermohydraulic model and the characteristics of solution in CHAN-2T code are introduced.
本文介绍了 CHAN-2T 程序的热工水力模型及求解方法的特点。
The RELAP4 / MOD7 is a large transient thermohydraulic calculation code which is licensed by American NRC for engineering examining.
RELAP4/MOD7程序是美国核管会批准用于工程审评的大型瞬态热工水力计算程序。
In the experimental research of reactor thermohydraulic behavior on test facility,an electric heater is always used instead of a nuclear reactor.
在利用热工水力台架进行反应堆热工水力研究时，一般采用电加热代替核释热。
A physical and thermohydraulic general estimate for the core of 25MW Lead Cooled Fast Breeder Reactor (LCFBR) has been carried out. The estimated result was compared with that of Sodium Cooled Fast Breeder Reactor (SCFBR) at the same power.
对25 MW电功率铅冷快增殖堆堆芯进行了物理和热工水力概算,并将计算结果与相同功率的钠冷快增殖堆的结果进行了分析比较。
The mechanism and process of thermal mixing of fluid with different temperature in a straight pipe were studied, which has general significance in nuclear reactor thermohydraulic process.
探讨了在核反应堆热工流体力学中具有普遍意义的不同温度流体达到热混合均匀状态的过程和机理。