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...
में बचाया:
मुख्य लेखक: | |
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स्वरूप: | इलेक्ट्रोनिक पुस्तक अध्याय |
भाषा: | अंग्रेज़ी |
प्रकाशित: |
KIT Scientific Publishing
2013
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श्रृंखला: | Karlsruher Forschungsberichte aus dem Institut für Hochleistungsimpuls- und Mikrowellentechnik
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विषय: | |
ऑनलाइन पहुंच: | DOAB: download the publication DOAB: description of the publication |
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सारांश: | 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 accuracy and reproducibility also during long term tests. Tolerable operating conditions concerning fretting wear by evaluating the specific wear coefficient and the concept of fretting maps are given. |
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भौतिक वर्णन: | 1 electronic resource (XV, 246 p. p.) |
आईएसबीएन: | KSP/1000031949 9783866449602 |
अभिगमन: | Open Access |