沸水堆

提出了小型热电联供沸水堆CR－200的一回路方案设计，用最佳热工水力估算程序RETRAN－02和编制的蒸发器设计程序对CR－200作了初步的一回路稳态热工设计和稳定性分析。

Small cogeneration boiling water reactor CR-200 is proposed , and its preliminary thermal-hydraulic design and stability analysis are completed with the best estimate thermal-hydraulic code RETRAN-02 and a steam generator design program .

先进沸水堆（ABWR）的特性与可用性

The Feature of ABWR and Its Availability

小型热电联供沸水堆cr-200研究。

Preliminary study on small cogeneration BWR cr-200 .

日立正在提供第三种设计&先进沸水堆（ABWR）。该技术已经在美国、台湾和日本获得牌照，但迄今仍未提交给英国监管机构审核。

Hitachi is offering a third design , the Advanced Boiling Water Reactor , which is already licensed in the US , Taiwan and Japan but has yet to be submitted to UK regulators .

低温堆和沸水堆流动不稳定因素比较分析

Factor Analysis of Flow Instability between Heating Reactor and Boiling Reactor

本文介绍了一个实用的沸水堆热工一水力模型。

A practical BWR thermal-hydraulic model has been introduced .

沸水堆核电站放射性废物管理与辐射防护的进展

Advances in radioactive wastes management and radiation protection at nuclear power plants with boiling water reactors

直接循环一体化沸水堆

Direct cycle integral boiling reactor

文中还给出了压水堆和沸水堆堆芯计算实例的比较。

The comparison of the computational results for reactor core of PWR and BWR are also presented .

我们的核电站是第三代压水堆，它比福岛的沸水堆安全。

Our plant type is a third-generation pressurised water reactor , and it is safer than the Fukushima boiling water reactor .

2沸水堆核电站模型的验证：通过程序稳态调试，与实际运行数据比较，对所建模型进行调试和修改，确保了模型正确性与可靠性。

BWR nuclear power plant model validation : compare the steady state calculation result with the actual operating data to ensure model accuracy and reliability .

从19世纪70年代投入运行以来，日本福岛第一核电站利用六个沸水堆，通过铀核裂变来产生热能。

In operation since the early1970s , Japan 's Fukushima Daiichi nuclear plant uses six boiling water reactors , which rely on uranium nuclear fission to generate heat .

面向网络的移动机械手遥操作控制技术研究这种传动不同于压水堆上使用的电磁-机械传动，也不同于沸水堆上使用的液压传动。

The Study of the Web-based Teleoperation Control Technique for the Mobile Manipulator ; The drive is different from electric-magnetic drive for PWR or hydraulic drive for BWR .

因此，建立一个准确完整的沸水堆核电站机理模型，对研究沸水堆特性以及两相流不稳定性问题有着重要的意义。

Therefore , to establish an accurate and complete BWR model is of great significance to the study of dynamic characteristics and two-phase flow instability problems of BWR .

分析表明：①自然循环系统中，欠热沸腾、冷凝、闪蒸是影响流动不稳定的重要因素，很多不稳定问题与此有关，这跟以沸水堆为背景的强迫循环系统有很大不同；

The anal-ysis shows : ① Sub-cooled boiling , condensation and flashing play an important role on the flow instabil-ities in a natural circulation system , and have connection with lots of instabilities , which is different to the forced circulation system ;

3控制系统建模：在模型基础上建立了沸水堆反应堆核电站的控制系统模型，对于电厂发生的变工况及故障工况能够进行实时的模拟，验证了控制系统的调控功能和抗干扰性。

BWR control system modeling : based on the model , establish the BWR reactor power plant control system , and complete the real-time simulation of variable conditions and fault conditions , which verify the regulatory functions and disturb resistance capacity of control system . 4 .