1. 发电原理
1. Philosophy of electricity producing
核燃料在核反应堆堆芯中进行链式反应，产生热能，同时燃料中的反应碎片的裂变速度变慢并消散其动能。这些热能必须被有效地，并且以相同速率带出堆芯，以防止堆芯过热，同时也把热能传送出堆芯。在堆芯外,热能被转变成另一种便于进一步利用的能源形式。一种流体就可以达到这个目的。在轻水堆中，轻水用作慢化剂和冷却剂。当冷却剂流经核燃料元件时，带走其产生的热量，以高温高压的形式储存在冷却剂里。
The nuclear chain reaction in the reactor core produces energy in the form of heat as the fission fragments slow down and dissipate their kinetic energy in the fuel. This heat must be removed efficiently and at the same rate it is being generated in order to prevent overheating of the core and to transport the energy outside the core where it can be converted to a convenient form for further utilization. A fluid is used for the purpose. In the light-water reactor case, water is used as both moderator and coolant. The energy transferred to the coolant, as it flows past the fuel elements, is stored in it in the form of temperature and pressure.
储存在冷却剂中的热量通过蒸汽汽轮机进一步转变成动能。最后通过蒸汽汽轮机把动能转换成电能并以这种能量形式通过电网传送给用户和传输系统。
The energy stored in the fluid is further converted into kinetic energy through a device called steam turbine. Finally, the kinetic energy is converted into electric power via steam turbine as the final energy form to be distributed to the consumers through the power grid and distribution system.
通过两个分开的但由蒸汽发生器相连的回路把热能从堆芯传送到汽轮机。蒸汽发生器是大型压水堆的构件，热量从主回路通过蒸汽发生器传送到第二回路，同时产生蒸汽。
The transport of thermal energy from the core to the turbine takes place through tow separated but interlocking loops, connected through steam generators. Steam generators are large PWR components in which heat form the primary circuit is transferred to the secondary with the production of steam.
2.压水堆的主要系统和构件
2. PWR Primary system and components
压水堆中的主回路一直保持在一个高压的状态下，压水堆以此而得名。这个压力通常是2200pis左右(大约15Mpa), 所以在反应堆容器中温度可以达到最高值。在这么大的压力下,水的沸点是343度，大于主回路中允许的水的最高温度332度。
The name of the PWR derives from that the primary circuit is kept at a very high pressure, typically around 2200 psi (equivalent to about 15 Mpa), such that at the maximum prevailing temperature in the boiling can occur. At 2200 psi, the boiling temperature of water is about 343℃, well above the maximum temperature of 332℃ allowed in the primary water.
压水堆核电站的基本环路和构件由以下组成:
The basic circuits and components of a PWR plant include mainly:
－ 包含反应堆堆芯的反应堆压力容器
－ The reactor pressure vessel, which contains the core.
－ 主要的冷却环路。这些环路构成了主要的压力装置.其中包括高压下的水循环环路,用于带走堆芯中裂变产生的热量.
－ The primary coolant circuit. These constitute the primary pressure boundary which contains water circulating at high pressure to remove fission- produced heat from the core.
－ 一个热交换器或者蒸汽发生器。热量经此被传送到第二回路。还包括一个生成蒸汽的水循环系统。
－ A heat exchanger or steam generator, in which heat in transferred to a secondary loop, also containing circulating water, where steam is generated.
－ 能量转换系统，把蒸汽转换成电能
－ The energy conversion system where steam is used to make electricity.
压水堆核电站最重要的构件有：反应堆压力容器和堆内构件，燃料束，控制棒和驱动装置，主冷却剂泵，稳压器，蒸汽发生器，汽轮机，冷凝器等。
The most important components of a PWR plant are reactor vessel and internals, fuel bundles, control rods and drive mechanism, primary coolant pump, pressurizer, steam generator, turbine, condenser, etc.
3. 压水堆容器的设计方案
3. PWR Containment Design
大多数的安全壳厂房是垂直的圆柱体型预应力后张拉钢筋砼结构，底部是一个扁平基础底板，筒体被一层钢衬里围着，上面是一个浅的穹顶。
Most of the Containment buildings are vertical cylindrical prestressed post-tensioned structures with a steel liner covered with a hemispherical or a shallow domed roof and with a flat foundation slab.
