Investigation of Fretting Wear of Cladding Materials in Liquid Lead
One promising concept for future nuclear reactors uses liquid metals like Pb as reactor coolant. In this work, fretting of fuel clad materials is investigated in Pb environment at relevant operating conditions. A novel test apparatus is presented that allows fretting tests in liquid lead with high a...
保存先:
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| フォーマット: | 電子媒体 図書の章 |
| 言語: | 英語 |
| 出版事項: |
KIT Scientific Publishing
2013
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| シリーズ: | Karlsruher Forschungsberichte aus dem Institut für Hochleistungsimpuls- und Mikrowellentechnik
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| 主題: | |
| オンライン･アクセス: | DOAB: download the publication DOAB: description of the publication |
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インターネット
DOAB: download the publicationDOAB: description of the publication
3rd Floor Main Library
| 請求記号: |
A1234.567 |
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| 所蔵 1 | 利用可 |