Polycrystalline Diamond Coating Protects Zr Cladding Surface Against Corrosion in Water-cooled Nuclear Reactors: Nuclear Fuel Durability Enhancement
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21730%2F18%3A00329816" target="_blank" >RIV/68407700:21730/18:00329816 - isvavai.cz</a>
Result on the web
<a href="https://onlinelibrary.wiley.com/doi/abs/10.1002/9781119407652.ch5" target="_blank" >https://onlinelibrary.wiley.com/doi/abs/10.1002/9781119407652.ch5</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1002/9781119407652.ch5" target="_blank" >10.1002/9781119407652.ch5</a>
Alternative languages
Result language
angličtina
Original language name
Polycrystalline Diamond Coating Protects Zr Cladding Surface Against Corrosion in Water-cooled Nuclear Reactors: Nuclear Fuel Durability Enhancement
Original language description
In this chapter we demonstrate a new strategy for the protection of zirconium (Zr) nuclear fuel cladding material by composite polycrystalline diamond (PCD) layers against corrosion in water-cooled nuclear reactors. We show that Zr alloy surfaces can be effectively protected against oxygen and hydrogen uptake at both accident and working temperatures in water-cooled nuclear reactor environments by coating the Zr surface with PCD layers grown in a microwave plasma chemical vapour deposition apparatus. The composition of PCD is not homogeneous – it contains diamond sp3-hybridized phase (96%) and soft sp2-hybridized C phase. This composition enables PCD layers to have suitable thermal expansion over a wide range of temperatures leading to no delamination. A key requirement is effective protection of Zr alloy surfaces against oxidation and hydration under standard operating conditions (360 °C). Oxidation of PCD-coated Zr alloy surfaces after more than 100 days in 360 °C hot water was significantly decreased (35-55%) compared with that of unprotected Zr alloy processed under the same conditions. Also at high temperatures (1100 °C), i.e. accident conditions, PCD layers may serve as passive elements for nuclear safety. PCD-protected Zr alloys also exhibited lower hydrogen concentrations than unprotected samples under all investigated conditions; in particular at accident conditions. After ion beam irradiation (10 dpa, 3 MeV Fe2+) PCD layers show satisfactory structural integrity with both sp3 and sp2 carbon phases present.
Czech name
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Czech description
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Classification
Type
C - Chapter in a specialist book
CEP classification
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OECD FORD branch
10304 - Nuclear physics
Result continuities
Project
<a href="/en/project/TE01020455" target="_blank" >TE01020455: Centre for Advanced Nuclear Technologies (CANUT)</a><br>
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Others
Publication year
2018
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Book/collection name
Advanced Coating Materials
ISBN
978-1-119-40763-8
Number of pages of the result
34
Pages from-to
123-156
Number of pages of the book
546
Publisher name
J. Wiley
Place of publication
New York
UT code for WoS chapter
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