谁有关于反应堆二回路的英文文献和配套的中文翻译，文献5-7页为最佳。求大神发给我，急死我了。

谁有关于反应堆二回路的英文文献和配套的中文翻译，文献5-7页为最佳。求大神发给我，急死我了。

The steam and power conversion system produces electrical power by driving a turbine generator rated at 900 MWe (maximum continuous output 983,8 MW) electrical output with steam from the nuclear steam supply system. The Turbine consists of a 3 000 rpm double flow HP and three double flow LP Cylinders and is directly connected, to the 26 000 volt, 3 phase, 50 Hz generator.

Equipment for regenerative feedwater heating, pumping to required pressure and various auxiliary systems complete the power conversion system. The only safety related system involves main steam from the steam generators to the bevel downstream of pipe restraint, feedwater piping from the bevel downstream of pipe restraint to the steam generator and the auxiliary feedwater system.

Main steam from the nuclear steam supply system flows through three Steam Lines to the live steam manifold located in the Turbine House, from the Live Steam Manifold steam lines provide steam to the Turbine Stop Valves, Deaerator, 1st and 2nd Stage Moisture Separator Reheaters, Steam Converter and turbine driven Feedwater Pumps. Main Steam enters the high pressure cylinder, flows through the blade paths, and exhausts to the moisture seperator reheaters where moisture is removed and the steam reheated, the steam then enters the low pressure cylinders, flows through the blade paths, and exhausts to the condenser.

Steam is extracted at selected points in the main turbine cycle for regenerative feedwater heating.

The condenser condenses the steam exhausted from the LP cylinders, together with steam exhausted from the Feedwater Pump turbine as well as other miscellaneous flows from the cycle. Condensate is taken from the condenser and is pumped by the condensate extraction pumps through the gland steam condenser (part flow), through three LP closed feedwater heaters to the deaerating feedwater heater and storage tank. Feedwater is then taken from this storage tank to the feedwater pumps and is pumped through the high pressure feedwater heaters to the steam generator inlets.

A turbine bypass system is capable of bypassing 85,15 % of the Maximum Reactor plant capability at full steam pressure, with Inlet Steam conditions of 66,3 bar abs, 0,32 per cent wet, at the NI/Cl interface.

The system design incorporates back-up means (power operated relief valves) for heat removal under any loss of normal heat sink, i.e., due to main steam stop valves trip, loss of circulating water flow, to accommodate reactor shutdown heat rejection requirements. The power operated relief valves also provide pressure control for hot shutdown.

2 x 50 % steam turbine driven and 1 x 50 % electric motor-driven feedwater pumps are provided to ensure that adequate feedwater is supplied to the steam generators for heat removal under all circumstances, including loss of electrical power and normal heat sink. A reduced amount of feedwater flow can be maintained until power is restored or until reactor decay heat removal can be accomplished by other systems.

蒸汽发电系统由核蒸汽供应系统供汽，驱动额定电输出功率为900MWe(最大持续出力为983.8MW)的汽轮发电机发电。汽机由一台3000rpm的双流高压缸和三台双流低压缸组成，并同26000V、3相、50Hz的发电机直接相连。

完整的蒸汽发电系统还包括给再生水加热并加压到所需压力的设备，以及各种辅助系统。由蒸汽发生器到管道约束支架下游管焊口的主蒸汽管道、由管道约束支架下游管焊口到蒸汽发生器的给水管道以及辅助给水系统是唯一的安全相关系统。

来自核蒸汽供应系统的主蒸汽，通过三条蒸汽管线流到汽机厂房内的新蒸汽支管。从新蒸汽支管出来的各条蒸汽管线分别向汽机截止阀、除氧器、第一二级汽水分离/再热器、蒸汽转换器和汽动给水泵供汽。主蒸汽进入高压缸，流经各级叶片流道，排入汽水分离/再热器，在那里去除水分并经过再热，然后进入低压缸，流经各级叶片流道，排入凝汽器。

在主汽机循环中选定的一些抽汽点抽出蒸汽，用于对水再生加热。

凝汽器将低压缸排出的蒸汽、给水泵汽机排出的蒸汽以及热力循环中其它各种来源的汽流进行冷凝。凝结水抽取泵唧送凝汽器内的凝结水，部分经密封蒸汽凝汽器(主要部分经三台低压闭式给水加热器)，流往给水除氧加热器和贮水箱。然后给水泵唧送该贮水箱的给水，经高压给水加热器流往蒸汽发生器进口。

在满载蒸汽压力下，当核岛和常规岛(NI/CI)界面处的蒸汽进口工况为66.3bara、0.32%湿度时，汽机旁路系统可以旁路电站最大蒸汽流量的85.15%。

系统设计还包括在任何正常热阱丧失时排走热量的备用手段(动力驱动卸压阀)，即在主蒸汽截止阀跳闸、循环水流量丧失时，能适应反应堆停堆后的排热需求。动力驱动卸压阀还可为热停堆提供压力控制。

装备了2台50%的汽动给水泵和一台50%的电动给水泵，以确保在所有情况下，包括电源丧失和正常热阱丧失情况下，向蒸汽发生器提供足够的给水以排走热量。降低流量的给水能维持到电源恢复，或者维持到其它系统可以把反应堆衰变热排出。追问这是片段，有论文没？追答全文涉及知识产权。你就在这个片段上自由发挥吧。