The moisture conditions of nuclear reactor concrete containment walls – an example for a BWR reactor

L. Nilsson, P. Johansson
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引用次数: 3

Abstract

A method is presented on how to quantify the moisture conditions of nuclear concrete containment walls. The method is based on first quantifying the boundary conditions at the outer and inner surfaces and then describing the moisture fixation and moisture transport within the concrete wall. The temperature and humidity conditions of the outdoor air and of the air close to the wall surfaces are monitored for a period of time and the vapour contents in the different points are compared. From the differences between the vapour contents the sources of moisture are identified and quantified. The previous and future climatic conditions are then predicted. An example is given for the conditions in the containment walls at Barseback nuclear power plant, where moisture measurements have been performed in situ and on samples taken from the walls.
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核反应堆混凝土安全壳的水分条件——以沸水堆反应堆为例
提出了一种量化核混凝土安全壳含水率的方法。该方法的基础是首先量化外表面和内表面的边界条件,然后描述混凝土墙内的水分固定和水分输送。监测了一段时间内室外空气和壁面附近空气的温湿度状况,比较了不同地点的水汽含量。根据水蒸气含量之间的差异,可以确定和量化水分的来源。然后预测过去和未来的气候条件。给出了巴塞贝克核电站安全壳条件的一个例子,在那里对从安全壳壁上采集的样品进行了现场水分测量。
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