Polycrystalline diamond and Cr double coatings protect Zr nuclear fuel tubes against accidental temperature corrosion in water-cooled nuclear reactors

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68378271%3A_____%2F24%3A00599381" target="_blank" >RIV/68378271:_____/24:00599381 - isvavai.cz</a>

Výsledek na webu

<a href="http://dx.doi.org/10.1007/978-3-031-45534-6_4" target="_blank" >http://dx.doi.org/10.1007/978-3-031-45534-6_4</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1007/978-3-031-45534-6_4" target="_blank" >10.1007/978-3-031-45534-6_4</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Polycrystalline diamond and Cr double coatings protect Zr nuclear fuel tubes against accidental temperature corrosion in water-cooled nuclear reactors

Popis výsledku v původním jazyce

The chapter proposes a new strategy for protecting Zr alloy nuclear fuel tubes from accidental temperature corrosion in water-cooled nuclear reactors. Protection of the zirconium alloy fuel tubes against accidental temperature corrosion in water-cooled nuclear reactors is important for the safety and efficiency of nuclear power plants, as corrosion in fuel tubes can lead to accidents and reduce the lifespan of the fuel. The new strategy of zirconium alloy fuel tubes from accidental temperature corrosion presented here involves a combination of polycrystalline diamond (PCD) and chromium (Cr) layers. The PCD layer prevents direct interaction between the Zr alloy surface and the hot water environment of the reactor, and releases carbon into the underlying Zr material to alter conditions for the penetration of oxygen and hydrogen. The Cr layer helps to reduce corrosion by forming carbides and improving adhesion of the coatings to the Zr alloy substrate.

Název v anglickém jazyce

Polycrystalline diamond and Cr double coatings protect Zr nuclear fuel tubes against accidental temperature corrosion in water-cooled nuclear reactors

Popis výsledku anglicky

The chapter proposes a new strategy for protecting Zr alloy nuclear fuel tubes from accidental temperature corrosion in water-cooled nuclear reactors. Protection of the zirconium alloy fuel tubes against accidental temperature corrosion in water-cooled nuclear reactors is important for the safety and efficiency of nuclear power plants, as corrosion in fuel tubes can lead to accidents and reduce the lifespan of the fuel. The new strategy of zirconium alloy fuel tubes from accidental temperature corrosion presented here involves a combination of polycrystalline diamond (PCD) and chromium (Cr) layers. The PCD layer prevents direct interaction between the Zr alloy surface and the hot water environment of the reactor, and releases carbon into the underlying Zr material to alter conditions for the penetration of oxygen and hydrogen. The Cr layer helps to reduce corrosion by forming carbides and improving adhesion of the coatings to the Zr alloy substrate.

Druh

C - Kapitola v odborné knize

CEP obor

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OECD FORD obor

20501 - Materials engineering

Projekt

<a href="/cs/project/TK02030069" target="_blank" >TK02030069: Energy Storage při produkci elektřiny</a><br>

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)<br>I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2024

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Název knihy nebo sborníku

Coatings for High-Temperature Environments

ISBN

978-3-031-45536-0

Počet stran výsledku

20

Strana od-do

83-102

Počet stran knihy

430

Název nakladatele

Springer Cham

Místo vydání

Cham

Kód UT WoS kapitoly

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