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(一)前言目前,水冷式原子能动力堆的燃料包复材料及压力管材料大都采用Zr—2,Zr—4合金,但很多设计者认为,这类锆合金不适于用在更高的温度下(比如400℃左右)使用。也很难使设计的许用应力进一步提高,这就在很大程度上限制了此类堆型的改进。据苏联,加拿大等国发表的资料认为Zr—Nb系合金很有使用前途,苏联已将Zr—1Nb合金用于水冷堆燃料包套管,加拿大已将Zr—2.5Nb合金用于有机冷却堆之燃料包套管及重水冷却堆之压力管;英,美,日,西德等也都
(I) Preface At present, most of the fuel clad materials and pressure pipe materials of water-cooled nuclear power reactor use Zr-2, Zr-4 alloy, but many designers think that this type of zirconium alloy is not suitable for use at higher temperatures (Such as 400 ℃ or so) to use. It is also difficult to further increase the design allowable stress, which greatly limits the improvement of such stacks. According to the data published by the Soviet Union, Canada and other countries that the Zr-Nb alloy is very promising, the Soviet Union has Zr-1Nb alloy used in water-cooled reactor fuel cladding, Canada has Zr-2.5Nb alloy used in the organic cooling reactor Fuel cladding tube and heavy water cooling reactor pressure pipe; Britain, the United States, Japan, West Germany and so on