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核反应堆用锆材的发展趋势与对策探讨 被引量:2

Development Trend of Zircaloy Materials for Nuclear Reactors and Our Policy toward the Development of Shanghai Zircaloy Industry
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摘要 本文综述核材料锆合金的发展概况及上海与国内外先进水平的主要差距。核电的发展要求沪产锆合金管进一步改善耐高温高压水腐蚀、提高高温强度和抵抗疲劳破损的能力。为此,文中着重讨论了管材的堆内行为、组织性能与生产工艺的关系,并在此基础上研讨振兴上海锆工业的策略。 The development of zircaloy materials for nuclear reactors is reviewed and the backward aspects of Shanghai zircaloy industry in comparison with foreign countries and other cities in China are pointed out. The development of nuclear power stations requests that the high temperature strength and resistance to high temperature-high pressure corrosion as well as to fatigue cracks of zircaloy materials manufactured in Shanghai should be further improved. In this paper,a special emphasis is laid on the discussion of relations between in-reactor behaviors, structural properties and production technology of zircaloy tubings. Based on the discussion, our policy toward the development of Shanghai zircaloy industry is suggested.
作者 杨永建
出处 《上海金属(有色分册)》 1990年第2期1-8,共8页
关键词 锆合金 燃料元件 包壳管 核反应堆 锆材 Nuclear power Zircaloy Fuel element Cladding tube
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