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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.

所以，我们有一个，2个障碍，相比于,沸水型反应堆的一个来说。So, we have one, two, barriers as compared to a single barrier for a BWR system.

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BWR是通过沸水来发电的，用它的蒸汽旋转涡轮实现这一功能。BWR produces electricity by boiling water, and spinning a a turbine with that steam.

由一个BWR生产电开水，旋转涡轮与蒸汽。A BWR produces electricity by boiling water, and spinning a a turbine with that steam.

而且，我们放入控制刀片,在操作过程中来控制沸水型反应堆的功率分布。In addition we put in control blades during operation to control power distribution in a BWR.

对一个沸水型反应堆来说，这是更细节的观点,关于反应堆核心来说，指出了几个功能。For a BWR this is a more detailed view of the reactor core, pointing out several of the functions.

沸水式反应堆的压力大约在1000磅,那使得沸腾可以在核心这个地方发生。The pressure in a BWR is about a thousand pounds which allows the boiling to take place in the core.

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所以加压水反应堆和沸水反应堆的不同,就是沸水反应堆的在抑压池里有个装置,使得蒸汽能够释放出来。So the big difference between a PWR and BWR is that a BWR has a built in suppression pool for the steam that maybe released.

这一个是很熟悉的，增压安全阀的疏忽打开,或者是在压水式反应堆的减压阀,或者是在沸水式反应堆的安全阀。This one is the familiar one, inadvertent opening of a pressurised safety or relief valve in a PWR or a safety valve in a BWR.

物理模拟了新FM锻造法，研究了料宽比和刚端长度对锻件体内应力的影响。The NEW FM is simulated by physical method. The influence of BWR and stiff length affecting stress in the forgings bodies is analyzed.

数值模拟分析了新FM法拔长时，不同的砧宽比、料宽比及压下率情况下，刚端长度对应力分布的影响。The influence of stiff length affecting stress distribution under different AWR, BWR and CR when stretching by NEM FM were simulated and analyzed.

沸水反应堆中包含数千根细长的中空管即燃料棒，它长3.6米，福岛第一核电厂中的燃料棒是锆合金制成的。A BWR contains thousands of thin, straw-like tubes 12 feet in length, known as fuel rods, that in the case of Fukushima are made of a zirconium alloy.

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你们可能使一个蒸汽发生器的管道破裂，也可能使一个仪器的线断裂,可能会得到管道破裂的光谱,在沸水式反应堆容器的里面。You could break a steam generator tube, you could break an instrument line and you could have a spectrum of pipe breaks in a BWR inside of containment.

它们的优势和不同,在压水式和沸水式反应堆里，就是在沸水式里，我们能在之后的课程里看到，有一个自动的降压系统。The advantage and the difference also between a PWR and a BWR is that in a BWR, as we'll see in future lectures, there is an automatic depressurisation system.

这是个沸水式反应堆和压水式反应堆的,设计上的重要区别，沸水型反应堆的燃料组件,是罐装起来确保我们得到,的冷水的供应足够。This is a very important design difference between a BWR and a PWR. So, BWR fuel assemblies are essentially canned to make sure we have an adequate supply of cooling water.

你们会注意到燃料组件的数量,在沸水式反应堆里，最高到,相比于，大约,240个组件在加压式冷却水反应堆里。And you'll notice the number of fuel assemblies 750 in a BWR is up around seven hundred and fifty 200 compared to around two hundred two hundred and forty fuel assemblies in a PWR.

还有很清楚地，许多不同种的燃料组件，如你们会在一个沸水型,和加压水式反应堆看到的,燃料组件是不同的，所有产生在一个燃料针的,热量都需要除去。And clearly, many different types of fuel assemblies, as you will see a BWR and PWR fuel assemblies are different and all heat that is generated in that one fuel pin needs to be removed.

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用准确度较高的BWR方程校核了其他状态方程，提出了将BWR状态方程运用于燃气管网水力计算的方法。The precisions of other state equations are checked with BWR equation which precision is very high. The method applying the BWR equation to gas network hydraulic calculation is proposed.

他们做了些研究，他们做了一些前期的,分析，他们让BWR的人修理,某些东西，但是他们总结出来,它对PWR当时没问题的，在当时。They did some research, they did some preliminary analysis and they basically had the BWR people fix certain things but they concluded that it was kind of okay for PWRs back at that time.

现在，沸水型反应堆的燃料组件是和特殊的,因为在核心的地方已经沸腾了,那就需要一个保险措施，能让每一个,燃料组件都能冷却并且得到水。Now BWR fuel assembly is unique in the sense that because we have boiling going on in the core there needs to be some assurance that every fuel assembly is getting coolant and getting water.