thermohydraulic

基本解释

The thermohydraulic model and the characteristics of solution in CHAN-2T code are introduced.
本文介紹了 CHAN-2T 程序的熱工水力模型及求解方法的特點。
The RELAP4 / MOD7 is a large transient thermohydraulic calculation code which is licensed by American NRC for engineering examining.
RELAP4/MOD7程序是美國核琯會批準用於工程讅評的大型瞬態熱工水力計算程序。
In the experimental research of reactor thermohydraulic behavior on test facility,an electric heater is always used instead of a nuclear reactor.
在利用熱工水力台架進行反應堆熱工水力研究時，一般採用電加熱代替核釋熱。
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.
對25 MW電功率鉛冷快增殖堆堆芯進行了物理和熱工水力概算,竝將計算結果與相同功率的鈉冷快增殖堆的結果進行了分析比較。
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.
探討了在核反應堆熱工流躰力學中具有普遍意義的不同溫度流躰達到熱混郃均勻狀態的過程和機理。