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Zirconium alloy and uranium oxide fuel development in india for nuclear power reactors

机译:印度用于核动力反应堆的锆合金和氧化铀燃料开发

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India is pursuing a self-reliant nuclear power programme since the last three decades. Presently, two Boiling Water Reactors (BWR) and ten Pressurised Heavy Water Reactors (PHWR) are in operation with total capacity of 2330 MWe and two more PHWR 220 MWe units would be commissioned by the end of the year 2000. The target is to set up 20,000 MWe nuclear power by 2020. The Nuclear Fuel Complex (NFC) at Hyderabad have been manufacturing zirconium alloy clad natural and enriched uranium oxide fuels for PHWRs and BWRs respectively. During the last two years, the production of Hf-free ZrO_2 powder and zirconium sponge and UO_2 powder, pellets and PHWR fuel assemblies have been enhanced significantly. The present paper summarises the manufacturing experience of these materials at NFC during recent years.
机译:自最近三十年以来,印度一直在推行自力更生的核电计划。目前,有两个沸水反应堆(BWR)和十个加压重水反应堆(PHWR)正在运行,总容量为2330 MWe,另外两个PHWR 220 MWe装置将在2000年底投入使用。目标是设定到2020年,核电总装机容量将达到20,000 MWe。海得拉巴的核燃料厂(NFC)一直在分别生产用于PHWR和BWR的锆合金包覆的天然和浓缩铀氧化物燃料。在过去的两年中,无Hf的ZrO_2粉末和海绵锆和UO_2粉末,球团和PHWR燃料组件的生产得到了显着提高。本文总结了近年来在NFC中这些材料的制造经验。

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