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
According to the development of reactor protection systems (RPS) an improved concept design of RPS for 200 MW nuclear heating plant (NHP) was covered in this paper.
根据保护系统的技术发展及最新的电子技术，并结合２００ＭＷ核供热站的特点，提出了一种改进的保护系统设计方案。
Based on the principle of hydraulic control rod driving system(HCRDS), the paper gives a new scram method, which makes the inside pressure of step cylinder discharge, to solve the scram problem of HCRDS in control rod hang up accident and inversion conditions, and some experiments were caried out with the 1∶1 experimental loop of the HCRDS for the 200 MW nuclear heating reactor(NHR200).
针对控制棒水力驱动系统在摩擦力卡棒和倒置等极限工况下的停堆问题,根据控制棒水力驱动系统的工作原理,提出了步进缸内腔卸压的解决方法,并在200MW低温核供热堆控制棒水力驱动系统的1∶1实验台架上进行了冷态实验。
Journal of Tsinghua University (Science and Technology), 1994, 34(52): 32-38 Investigation on heat-electricity cogeneration with nuclear heating reactors;
核供热反应堆热电联产实验研究
Pressure reducing and loss of water under SBLOCA at upper plenum of nuclear heating reactors;
在５ＭＷ核供热反应堆的模拟实验台架ＨＲＴＬ－５上进行了上空腔破口失水事故实验研究，给出了压力衰减和失水量的实验结果。