| 书目名称 | U Uranium | | 副标题 | Behavior of Uranium | | 编辑 | Helmut Aßmann,Erich Merz,Gilbert N. Walton,Karl-Ch | | 视频video | | | 丛书名称 | Gmelin Handbook of Inorganic and Organometallic Chemistry - 8th edition | | 图书封面 |  | | 描述 | The present volume A4 of the "Uranium" series of the Gmelin Handbook deals with two very important technological aspects of the nuclear fuel cycle: - the behavior of fuel elements during burnup in a nuclear reactor, and - the reprocessing of spent fuel to recover the non-fissioned uranium and newly created materials. The usefullifetime of a fuel element in a nuclear reactor depends strongly on the change of its chemical and physical properties during irradiation. Properties like thermal conductivity, swelling, creep, and oxygen-to-metal ratio are strongly affected by the intense neutron field and the energetic fission products. Furthermore, the high temperature gradient in a fuel element also produces alterations of the initial fuel. such as densification or U: Pu segregation. All of these effects are thoroughly discussed for the different kinds of fuels to be used in modern nuclear reactors today or in the future. The vast amount of very often Contradietory results in sometimes difficultly obtainable Iiterature has been summarized to create a compendium in this field with the two sections, on oxide and on carbide and nitride fuels, respectively. The chapters on reprocessing of spe | | 出版日期 | Book 1981Latest edition | | 关键词 | Kernbrennstoff; Neutron; behavior; element; fission; nuclear fuel; nuclear reactor; oxygen; radiation; segreg | | 版次 | 8 | | doi | https://doi.org/10.1007/978-3-662-06014-8 | | isbn_ebook | 978-3-662-06014-8 | | copyright | Springer-Verlag Berlin Heidelberg 1981 |
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发表于 2025-3-21 16:13:55
